WorldWideScience

Sample records for safety initiative sacsi

  1. Comprehensive School Safety Initiative Report

    Science.gov (United States)

    National Institute of Justice, 2014

    2014-01-01

    The National Institute of Justice (NIJ) developed the Comprehensive School Safety Initiative in consultation with federal partners and Congress. It is a research-focused initiative designed to increase the safety of schools nationwide through the development of knowledge regarding the most effective and sustainable school safety interventions and…

  2. Nuclear materials facility safety initiative

    International Nuclear Information System (INIS)

    Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

    2000-01-01

    Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

  3. Implementing Patient Safety Initiatives in Rural Hospitals

    Science.gov (United States)

    Klingner, Jill; Moscovice, Ira; Tupper, Judith; Coburn, Andrew; Wakefield, Mary

    2009-01-01

    Implementation of patient safety initiatives can be costly in time and energy. Because of small volumes and limited resources, rural hospitals often are not included in nationally driven patient safety initiatives. This article describes the Tennessee Rural Hospital Patient Safety Demonstration project, whose goal was to strengthen capacity for…

  4. Dicty_cDB: VHN647 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available ignments: (bits) Value CP001577_292( CP001577 |pid:none) Micromonas sp. RCC299 chromosome... 106 2e-21 (Q9NZJ4) RecName: Full=Sacsi...n; &AL157766_4( AL157766 |pid:none) 105 5e-21 BC138482_1( BC138482 |pid:none) Mus musculus sacsi..... 103 2e-20 (Q9JLC8) RecName: Full=Sacsin; 103 2e-20 BC171956_1( BC171956 |pid:none) Mus musculus sacsi

  5. An evaluation of safety culture initiatives at BNSF Railway

    Science.gov (United States)

    2015-04-01

    Major safety culture (SC) initiatives initiated in the FRA Office of Research, Technology and Development (RT&D), such as Clear Signal for Action (CSA), the Investigation of Safety Related Occurrences Protocol (ISROP), the Participative Safety Rules ...

  6. DIPS space exploration initiative safety

    International Nuclear Information System (INIS)

    Dix, T.E.

    1991-01-01

    The Dynamic Isotope Power Subsystem has been identified for potential applications for the Space Exploration Initiative. A qualitative safety assessment has been performed to demonstrate the overall safety adequacy of the Dynamic Isotope Power Subsystem for these applications. Mission profiles were defined for reference lunar and martian flights. Accident scenarios were qualitatively defined for all mission phases. Safety issues were then identified. The safety issues included radiation exposure, fuel containment, criticality, diversion, toxic materials, heat flux to the extravehicular mobility unit, and disposal. The design was reviewed for areas where safety might be further improved. Safety would be improved by launching the fuel separate from the rest of the subsystem on expendable launch vehicles, using a fuel handling tool during unloading of the hot fuel canister, and constructing a cage-like structure around the reversible heat removal system lithium heat pipes. The results of the safety assessment indicate that the DIPS design with minor modifications will produce a low risk concept

  7. Radiation safety without borders initiative

    International Nuclear Information System (INIS)

    Dibblee, Martha; Dickson, Howard; Krieger, Ken; Lopez, Jose; Waite, David; Weaver, Ken

    2008-01-01

    The Radiation Safety Without Borders (RSWB) initiative provides peer support to radiation safety professionals in developing countries, which bolsters the country's infrastructure and may lead the way for IRPA Associate membership. The Health Physics Society (HPS) recognizes that many nations do not possess the infrastructure to adequately control and beneficially use ionizing radiation. In a substantial number of countries, organized radiation protection programs are minimal. The RSWB initiative relies on HPS volunteers to assist their counterparts in developing countries with emerging health physics and radiation safety programs, but whose resources are limited, to provide tools that promote and support infrastructure and help these professionals help themselves. RSWB experience to date has shown that by providing refurbished instruments, promoting visits to a HPS venue, or visiting a country just to look provide valuable technical and social infrastructure experiences often missing in the developing nation's cadre of radiation safety professionals. HPS/RSWB with the assistance of the International Atomic Energy Agency (IAEA) pairs chapters with a country, with the expectation that the country's professional radiation safety personnel will form a foreign HPS chapter, and the country eventually will become an IRPA Associate. Although still in its formative stage, RSWB nonetheless has gotten valuable information in spite of the small number of missions. The RSWB initiative continues to have significant beneficial impacts, including: Improving the radiation safety infrastructure of the countries that participate; Assisting those countries without professional radiation safety societies to form one; Strengthening the humanitarian efforts of the United States; Enhancing Homeland Security efforts through improved control of radioactive material internationally. Developing countries, including those in Latin America, underwritten by IAEA, may take advantage of resources

  8. Dicty_cDB: VHF491 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available ents: (bits) Value BC142916_1( BC142916 |pid:none) Danio rerio hypothetical LOC555303... 97 6e-19 (Q9NZJ4) RecName: Full=Sacsi...n; &AL157766_4( AL157766 |pid:none) 97 9e-19 BC171956_1( BC171956 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 96 1e-18 BC138482_1( BC138482 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 96 2e-18 (Q9JLC8) RecName: Full=Sacsin; 96 2e-18 CP001577_292( CP001577 |pid:none) Mi

  9. Preparation of the initial safety case

    International Nuclear Information System (INIS)

    Hensley, G.

    1987-01-01

    In British Nuclear Fuels plc (BNFL), the design of nuclear chemical plants for construction and subsequent operation at Sellafield Works is carried out by the Engineering Division of the Spent Fuel Management Services Group based at Risley, Warrington. Plant construction cannot take place, nor plant commissioning, until it has been demonstrated in the initial (design) safety case that the chosen design will allow the plant to be operated in an adequately safe manner, corresponding to an extremely low level of risk. The safety documentation procedure is described. A Preliminary Design Safety Appraisal is made of the initial design proposal to give an early indication of the order of risk that might prevail. The risk from each hazard is compared with an allocated risk target which makes up a proportion of the total plant risk which is quantified in BNFL's risk criteria. Where the risk appears unacceptable, appropriate modifications are made to the design. Prior to commissioning, a comprehensive, detailed risk assessment is carried out. The methodology of probabilistic risk assessment is described and examples given of how different hazards are assessed. (author)

  10. Community Road Safety Initiatives for the Minerals Industry

    Directory of Open Access Journals (Sweden)

    Tim Horberry

    2013-12-01

    Full Text Available Major companies in the minerals industry are increasingly recognizing that their operations have an impact in the wider community. Regarding transportation issues, this impact extends beyond purely the safety of company vehicle fleets to consideration of Community Road Safety (CRS concerns, which address the driving, walking, and riding practices of community members in a locale with increased heavy vehicle traffic. Our assessment here of national and international trends in approaches to road safety awareness and associated road safety strategies is meant to inform companies in the minerals industry of developments that can influence the design of their road safety initiatives. The review begins by considering the overall road safety context and the dominant “safe systems” framework employed internationally. Thereafter, it considers what is typically included in CRS initiatives for the minerals industry. Three case studies are then presented to highlight approaches that feature exemplary collaboration, design, implementation, or impact. Thereafter, we analyze lessons learnt by key researchers and practitioners in the CRS field. Finally, we conclude that best CRS practices for the minerals industry rely on eleven factors, including for example collaboration with local entities and stepwise implementation.

  11. 76 FR 29773 - Call for Participation in Pillbox Patient-Safety Initiative

    Science.gov (United States)

    2011-05-23

    ... Pillbox Patient-Safety Initiative ACTION: Notice. SUMMARY: The National Library of Medicine (NLM) invites..., production version of Pillbox. This initiative is an important element of ongoing efforts to enhance patient.... SUPPLEMENTARY INFORMATION: NLM has established Pillbox, an initiative to enhance patient safety, by making...

  12. Surgical Safety Training of World Health Organization Initiatives.

    Science.gov (United States)

    Davis, Christopher R; Bates, Anthony S; Toll, Edward C; Cole, Matthew; Smith, Frank C T; Stark, Michael

    2014-01-01

    Undergraduate training in surgical safety is essential to maximize patient safety. This national review quantified undergraduate surgical safety training. Training of 2 international safety initiatives was quantified: (1) World Health Organization (WHO) "Guidelines for Safe Surgery" and (2) Department of Health (DoH) "Principles of the Productive Operating Theatre." Also, 13 additional safety skills were quantified. Data were analyzed using Mann-Whitney U tests. In all, 23 universities entered the study (71.9% response). Safety skills from WHO and DoH documents were formally taught in 4 UK medical schools (17.4%). Individual components of the documents were taught more frequently (47.6%). Half (50.9%) of the additional safety skills identified were taught. Surgical societies supplemented safety training, although the total amount of training provided was less than that in university curricula (P < .0001). Surgical safety training is inadequate in UK medical schools. To protect patients and maximize safety, a national undergraduate safety curriculum is recommended. © 2013 by the American College of Medical Quality.

  13. Software Dependability and Safety Evaluations ESA's Initiative

    Science.gov (United States)

    Hernek, M.

    ESA has allocated funds for an initiative to evaluate Dependability and Safety methods of Software. The objectives of this initiative are; · More extensive validation of Safety and Dependability techniques for Software · Provide valuable results to improve the quality of the Software thus promoting the application of Dependability and Safety methods and techniques. ESA space systems are being developed according to defined PA requirement specifications. These requirements may be implemented through various design concepts, e.g. redundancy, diversity etc. varying from project to project. Analysis methods (FMECA. FTA, HA, etc) are frequently used during requirements analysis and design activities to assure the correct implementation of system PA requirements. The criticality level of failures, functions and systems is determined and by doing that the critical sub-systems are identified, on which dependability and safety techniques are to be applied during development. Proper performance of the software development requires the development of a technical specification for the products at the beginning of the life cycle. Such technical specification comprises both functional and non-functional requirements. These non-functional requirements address characteristics of the product such as quality, dependability, safety and maintainability. Software in space systems is more and more used in critical functions. Also the trend towards more frequent use of COTS and reusable components pose new difficulties in terms of assuring reliable and safe systems. Because of this, its dependability and safety must be carefully analysed. ESA identified and documented techniques, methods and procedures to ensure that software dependability and safety requirements are specified and taken into account during the design and development of a software system and to verify/validate that the implemented software systems comply with these requirements [R1].

  14. Safety and Security Interface Technology Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-05-01

    Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis

  15. Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

    Science.gov (United States)

    Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

    1993-01-01

    An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

  16. A comparative review of patient safety initiatives for national health information technology

    DEFF Research Database (Denmark)

    Magrabi, Farah; Aarts, Jos; Nøhr, Christian

    2013-01-01

    OBJECTIVE: To collect and critically review patient safety initiatives for health information technology (HIT). METHOD: Publicly promulgated set of advisories, recommendations, guidelines, or standards potentially addressing safe system design, build, implementation or use were identified...... by searching the websites of regional and national agencies and programmes in a non-exhaustive set of exemplar countries including England, Denmark, the Netherlands, the USA, Canada and Australia. Initiatives were categorised by type and software systems covered. RESULTS: We found 27 patient safety initiatives...... were aimed at certification in the USA, Canada and Australia. Safety is addressed alongside interoperability in the Australian certification programme but it is not explicitly addressed in the US and Canadian programmes, though conformance with specific functionality, interoperability, security...

  17. Dicty_cDB: VHE271 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available -21 (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 105 3e-21 BC171956_1( BC171956 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 103 1e-20 BC138482_1( BC138482 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 103 1e-20 (Q9JLC8) RecName: Full=Sacsin; 103 1e-20 AB006708_10( AB006

  18. Leadership and Safety Management: Regulatory Initiatives for Enhancing Nuclear Safety in the Republic of Korea

    International Nuclear Information System (INIS)

    Yun, C.H.; Park, Y.W.; Choi, K.S.

    2010-01-01

    Since the construction of the first nuclear power plant (NPP) in the Republic of Korea in 1978, a high level of nuclear safety has continued to be maintained. This has been the important basis on which the continuous construction of NPPs has been possible in the country. To date, regulatory initiatives, leaderships and strategies adopting well harmonized regulatory systems and practices of advanced countries have contributed to improving the effectiveness and efficiency of safety regulation and further enhancing nuclear safety. The outcomes have resulted in a high level of safety and performance of Korean NPPs, attributing largely to the safety promotion policy. Recently, with the support of the Korean Ministry of Education, Science and Technology (MEST), the Korea Institute of Nuclear Safety (KINS) established the International Nuclear Safety School and created a Nuclear Safety Master's Degree Programme. Further, it developed multilateral and bilateral cooperation with other agencies to promote global nuclear safety, with the aim of providing knowledge and training to new entrant countries in establishing the safety infrastructure necessary for ensuring an acceptable level of nuclear safety. (author)

  19. Safety and Security Interface Technology Initiative

    International Nuclear Information System (INIS)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-01-01

    Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. ''Supporting Excellence in Operations Through Safety Analysis'', (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is ''Safeguards/Security Integration with Safety''. This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ''tool box'' of information/successes. Specific Benefits. The expectation or end state resulting from the topical report and associated

  20. Patient safety initiatives in Central and Eastern Europe: A mixed methods approach by the LINNEAUS collaboration on patient safety in primary care

    Science.gov (United States)

    Godycki-Cwirko, Maciek; Esmail, Aneez; Dovey, Susan; Wensing, Michel; Parker, Dianne; Kowalczyk, Anna; Błaszczyk, Honorata; Kosiek, Katarzyna

    2015-01-01

    ABSTRACT Background: Despite patient safety being recognized as an important healthcare issue in the European Union, there has been variable implementation of patient safety initiatives in Central and Eastern Europe (CEE). Objective: To assess the status of patient safety initiatives in countries in CEE; to describe a process of engagement in Poland, which can serve as a template for the implementation of patient safety initiatives in primary care. Methods: A mixed methods design was used. We conducted a review of literature focusing on publications from CEE, an inventory of patient safety initiatives in CEE countries, interviews with key informants, international survey, review of national reporting systems, and pilot demonstrator project in Poland with implementation of patient safety toolkits assessment. Results: There was no published patient safety research from Albania, Belarus, Greece, Latvia, Lithuania, Romania, or Russia. Nine papers were found from Bulgaria, Croatia, the Czech Republic, Poland, Serbia, and Slovenia. In most of the CEE countries, patient safety had been addressed at the policy level although the focus was mainly in hospital care. There was a dearth of activity in primary care. The use of patient improvement strategies was low. Conclusion: International cooperation as exemplified in the demonstrator project can help in the development and implementation of patient safety initiatives in primary care in changing the emphasis away from a blame culture to one where greater emphasis is placed on improvement and learning. PMID:26339839

  1. Danish initiatives to improve the safety of meat products

    DEFF Research Database (Denmark)

    Wegener, Henrik Caspar

    2010-01-01

    and Campylobacter, and to a lesser extent Yersinia, Escherichia coli O157 and Listeria. Danish initiatives to improve the safety of meat products have focused on the entire production chain from the farm to the consumer, with a special emphasis on the pre-harvest stage of production. The control of bacterial......During the last two decades the major food safety problems in Denmark, as determined by the number of human patients, has been associated with bacterial infections stemming from meat products and eggs. The bacterial pathogens causing the majority of human infections has been Salmonella...

  2. Initial state report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Pers, Karin (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

    2006-10-15

    A comprehensive description of the initial state of the engineered parts of the repository system is one of the main bases for the safety assessment. There is no obvious definition of the time of the initial state. For the engineered part of their repository system, the time of deposition is a natural starting point and the initial state in SR-Can is, therefore, defined as the state at the time of deposition for the engineered barrier system. The initial state of the engineered parts of the repository system is largely obtained from the design specifications of the repository, including allowed tolerances or allowance for deviations. Also the manufacturing, excavation and control methods have to be described in order to adequately discuss and handle hypothetical initial states outside the allowed limits in the design specifications. It should also be noted that many parts of the repository system are as yet not finally designed, there can be many changes in the future. The design and technical solutions presented here are representative of the current stage of development. The repository system is based on the KBS-3 method, in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at 400-700 m depth in saturated granitic rock. The facility design comprises rock caverns, tunnels, deposition positions etc. Deposition tunnels are linked by tunnels for transport and communication and shafts for ventilation. One ramp and five shafts connect the surface facility to the underground repository. The ramp is used for heavy and bulky transports and the shafts are for utility systems and for transport of excavated rock, backfill and staff. For the purposes of the safety assessment, the engineered parts of the repository system have been sub-divided into a number of components or sub-systems. These are: The fuel, (also including cavities in the canister since strong interactions between the two occur if the

  3. Initial state report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Pers, Karin

    2006-10-01

    A comprehensive description of the initial state of the engineered parts of the repository system is one of the main bases for the safety assessment. There is no obvious definition of the time of the initial state. For the engineered part of their repository system, the time of deposition is a natural starting point and the initial state in SR-Can is, therefore, defined as the state at the time of deposition for the engineered barrier system. The initial state of the engineered parts of the repository system is largely obtained from the design specifications of the repository, including allowed tolerances or allowance for deviations. Also the manufacturing, excavation and control methods have to be described in order to adequately discuss and handle hypothetical initial states outside the allowed limits in the design specifications. It should also be noted that many parts of the repository system are as yet not finally designed, there can be many changes in the future. The design and technical solutions presented here are representative of the current stage of development. The repository system is based on the KBS-3 method, in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at 400-700 m depth in saturated granitic rock. The facility design comprises rock caverns, tunnels, deposition positions etc. Deposition tunnels are linked by tunnels for transport and communication and shafts for ventilation. One ramp and five shafts connect the surface facility to the underground repository. The ramp is used for heavy and bulky transports and the shafts are for utility systems and for transport of excavated rock, backfill and staff. For the purposes of the safety assessment, the engineered parts of the repository system have been sub-divided into a number of components or sub-systems. These are: The fuel, (also including cavities in the canister since strong interactions between the two occur if the

  4. Initialization of Safety Assessment Process for the Croatian Radioactive Waste repository on Trgovska gora

    International Nuclear Information System (INIS)

    Lokner, V.; Levanat, I.; Subasic, D.

    2000-01-01

    An iterative process of safety assessment, presently focusing on the site-specific evaluation of the post-closure phase for the prospective LILW repository on Trgovska gora in Croatia, has recently been initiated. The primary aim of the first assessment iterations is to provide the experts involved, the regulators and the general public with a reasonable assurance that the applicable long term performance and safety objectives can be met. Another goal is to develop a sufficient understanding of the system behavior to support decisions about the site investigation, the facility design, the waste acceptance criteria and the closure conditions. In this initial phase, the safety assessment is structured in a manner following closely methodology of the ISAM. The International Programme for Improving Long Term Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities the IAEA coordinated research program started in 1997. Results of the safety assessment first iteration will be organized and presented in the form of a preliminary safety analysis report (PSAR), expected to be completed in the second part of the year 2000. As the first report on the initiated safety assessment activities, the PSAR will describe the concept and aims of the assessment process. Particular emphasis will be placed on description of the key elements of a safety assessment approach by: a) defining the assessment context; b) providing description of the disposal system; c) developing and justifying assessment scenarios; d) formulating and implementing models; and e) interpreting the scoping calculations. (author)

  5. Initiating events in the safety probabilistic analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Stasiulevicius, R.

    1989-01-01

    The importance of the initiating event in the probabilistic safety analysis of nuclear power plants are discussed and the basic procedures necessary for preparing reports, quantification and grouping of the events are described. The examples of initiating events with its occurence medium frequency, included those calculated for OCONEE reactor and Angra-1 reactor are presented. (E.G.)

  6. Initial development of a practical safety audit tool to assess fleet safety management practices.

    Science.gov (United States)

    Mitchell, Rebecca; Friswell, Rena; Mooren, Lori

    2012-07-01

    Work-related vehicle crashes are a common cause of occupational injury. Yet, there are few studies that investigate management practices used for light vehicle fleets (i.e. vehicles less than 4.5 tonnes). One of the impediments to obtaining and sharing information on effective fleet safety management is the lack of an evidence-based, standardised measurement tool. This article describes the initial development of an audit tool to assess fleet safety management practices in light vehicle fleets. The audit tool was developed by triangulating information from a review of the literature on fleet safety management practices and from semi-structured interviews with 15 fleet managers and 21 fleet drivers. A preliminary useability assessment was conducted with 5 organisations. The audit tool assesses the management of fleet safety against five core categories: (1) management, systems and processes; (2) monitoring and assessment; (3) employee recruitment, training and education; (4) vehicle technology, selection and maintenance; and (5) vehicle journeys. Each of these core categories has between 1 and 3 sub-categories. Organisations are rated at one of 4 levels on each sub-category. The fleet safety management audit tool is designed to identify the extent to which fleet safety is managed in an organisation against best practice. It is intended that the audit tool be used to conduct audits within an organisation to provide an indicator of progress in managing fleet safety and to consistently benchmark performance against other organisations. Application of the tool by fleet safety researchers is now needed to inform its further development and refinement and to permit psychometric evaluation. Copyright © 2012 Elsevier Ltd. All rights reserved.

  7. Effects of Implemented Initiatives on Patient Safety Culture in Fateme Al-zahra Hospital in Najafabad

    Directory of Open Access Journals (Sweden)

    Ahmadreza Izadi

    2015-01-01

    Full Text Available Introduction: Patient safety improvement requires ongoing culture. This cultural change is the most important challenge that managers are faced with in creation of a safe system. This study aims to show the results of initiatives to improvement in patient safety culture in Fateme Al-zahra hospital. Method: In the quasi-experimental research, patient safety culture was measured using the Persian questionnaire on adaptation of the hospital survey on patient safety culture in 12 dimensions. The research was conducted before (January 2010 and after (September 2012 the improvement initiatives. In this study, all units were determined and no sampling method was used. Reliability of the questionnaire was tested by Alpha Chronbakh (0.83. Data were analyzed using descriptive statistics indices and Independent T-Test by SPSS Software (version 18. Results: 350 questionnaires were distributed in each phaseand overall response rate was 58 and 56 percent, respectively. According to Independent T-test, Management expectations and actions, Organizational learning, Management support, Feedback and communication about error, Communication openness, Overall Perceptions of Safety, Non-punitive Response to Error, Frequency of Event Reporting, and Patient safety culture showed significant differences (P-value0.05. The mean score of Patient safety culture was 2.27 (from 5 and it was increased to 2.46 after initiatives that showed a significant difference (P-value<0.05. Conclusion: Although, improvement in patient safety culture needs teamwork and continuous attempts, the study showed that initiatives implemented in the case hospital had been effective in some dimensions. However, Teamwork within hospital units, Teamwork across units, Hospital handoffs and transitions, and Staffing dimensions were recognized for further intervention. Hospital could improve the patient safety culture with planning and measures in these dimensions.

  8. Determination of Initial Conditions for the Safety Analysis by Random Sampling of Operating Parameters

    International Nuclear Information System (INIS)

    Jeong, Hae-Yong; Park, Moon-Ghu

    2015-01-01

    In most existing evaluation methodologies, which follow a conservative approach, the most conservative initial conditions are searched for each transient scenario through tremendous assessment for wide operating windows or limiting conditions for operation (LCO) allowed by the operating guidelines. In this procedure, a user effect could be involved and a remarkable time and human resources are consumed. In the present study, we investigated a more effective statistical method for the selection of the most conservative initial condition by the use of random sampling of operating parameters affecting the initial conditions. A method for the determination of initial conditions based on random sampling of plant design parameters is proposed. This method is expected to be applied for the selection of the most conservative initial plant conditions in the safety analysis using a conservative evaluation methodology. In the method, it is suggested that the initial conditions of reactor coolant flow rate, pressurizer level, pressurizer pressure, and SG level are adjusted by controlling the pump rated flow, setpoints of PLCS, PPCS, and FWCS, respectively. The proposed technique is expected to contribute to eliminate the human factors introduced in the conventional safety analysis procedure and also to reduce the human resources invested in the safety evaluation of nuclear power plants

  9. Flibe Use in Fusion Reactors - An Initial Safety Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, Lee Charles; Longhurst, Glen Reed

    1999-04-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF2) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material.

  10. Flibe use in fusion reactors: An initial safety assessment

    International Nuclear Information System (INIS)

    Cadwallader, L.C.; Longhurst, G.R.

    1999-01-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF 2 ) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material

  11. Defining initiating events for purposes of probabilistic safety assessment

    International Nuclear Information System (INIS)

    1993-09-01

    This document is primarily directed towards technical staff involved in the performance or review of plant specific Probabilistic Safety Assessment (PSA). It highlights different approaches and provides typical examples useful for defining the Initiating Events (IE). The document also includes the generic initiating event database, containing about 300 records taken from about 30 plant specific PSAs. In addition to its usefulness during the actual performance of a PSA, the generic IE database is of the utmost importance for peer reviews of PSAs, such as the IAEA's International Peer Review Service (IPERS) where reference to studies on similar NPPs is needed. 60 refs, figs and tabs

  12. Safety, feasibility and efficacy of a rapid ART initiation in pregnancy ...

    African Journals Online (AJOL)

    Safety, feasibility and efficacy of a rapid ART initiation in pregnancy pilot programme in Cape Town, South Africa. S Black, R Zulliger, L Myer, R Marcus, S Jeneker, R Taliep, D Pienaar, R Wood, L-G Bekker ...

  13. Expensive blood safety initiatives may offer less benefit than we think

    DEFF Research Database (Denmark)

    Kamper-Jørgensen, Mads; Hjalgrim, Henrik; Edgren, Gustaf

    2010-01-01

    Various blood safety initiatives have ensured a historically low risk of infection transmission through blood transfusion. Although further prevention of infection transmission is possible through, for example, nucleic acid testing and future introduction of pathogen inactivation, such initiative...... are very costly in relation to the benefit they offer. Although estimation of the cost-effectiveness requires detailed information about the survival of transfusion recipients, previous cost-effectiveness analyses have relied on incorrect survival assumptions....

  14. Flibe use in fusion reactors -- An initial safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, L.C.; Longhurst, G.R.

    1999-03-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF{sub 2}) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material.

  15. DOE spent nuclear fuel -- Nuclear criticality safety challenges and safeguards initiatives

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1994-01-01

    The field of nuclear criticality safety is confronted with growing technical challenges and the need for forward-thinking initiatives to address and resolve issues surrounding economic, safe and secure packaging, transport, interim storage, and long-term disposal of spent nuclear fuel. These challenges are reflected in multiparameter problems involving optimization of packaging designs for maximizing the density of material per package while ensuring subcriticality and safety under variable normal and hypothetical transport and storage conditions and for minimizing costs. Historic and recently revealed uncertainties in basic data used for performing nuclear subcriticality evaluations and safety analyses highlight the need to be vigilant in assessing the validity and range of applicability of calculational evaluations that represent extrapolations from ''benchmark'' data. Examples of these uncertainties are provided. Additionally, uncertainties resulting from the safeguarding of various forms of fissionable materials in transit and storage are discussed

  16. Gclust Server: 144530 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available 144530 HSA_38230498 Cluster Sequences - 4432 NP_055178.2 sacsin ; no annotation 1 1...ences Cluster Sequences Link to related sequences - Sequence length 4432 Representative annotation NP_055178.2 sacsi

  17. Short-term initiatives for enhancing cyber-safety within South African schools

    Directory of Open Access Journals (Sweden)

    Elmarie Kritzinger

    2016-07-01

    Full Text Available The rate of technological development across the globe is dramatic. The decreasing cost and increasing availability of ICT devices means that its users are no longer exclusively industry or government employees – they are now also home users. Home users integrate ICT in their daily lives for education, socialising and information gathering. However, using ICT is associated with risks and threats, such as identity theft and phishing scams. Most home users of ICT do not have the necessary information technology and Internet skills to protect themselves and their information. School learners, in particular, are not sufficiently educated on how to use technological devices safely, especially in developing countries such as South Africa. The national school curriculum in South Africa currently does not make provision for cyber-safety education, and the availability of supporting material and training for ICT teachers in South Africa is limited, resulting in a lack of knowledge and skills regarding cyber-safety. The research in hand focuses on the situation concerning cyber-safety awareness in schools and has adopted a short-term approach towards cyber-safety among teachers and school learners in South Africa until a formal long-term national approach has been implemented. This study takes a quantitative approach to investigating the current options of teachers to enhance cyber-safety among learners in their schools. The research proposes that short-term initiatives (i.e. posters can increase learners’ awareness of cyber-safety until formal cyber-safety awareness methods have been introduced.

  18. Report to the Attorney General on Body Armor Safety Initiative Testing and Activities

    National Research Council Canada - National Science Library

    2005-01-01

    On November 17, 2003, Attorney General John Ashcroft announced the U.S. Department of Justice's Body Armor Safety Initiative in response to concerns from the law enforcement community regarding the effectiveness of body armor in use...

  19. Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions.

    Science.gov (United States)

    Jarrar, Mu'taman; Abdul Rahman, Hamzah; Don, Mohammad Sobri

    2015-10-20

    Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patient safety. The country health plan of Ministry of Health (MOH) Malaysia and the MOH Malaysia Annual Reports were reviewed. The MOH has set four strategies for optimizing quality and sustaining quality of life. The 10th Malaysia Health Plan promotes the theme "1 Care for 1 Malaysia" in order to sustain the quality of care. Despite of these efforts, the total number of complaints received by the medico-legal section of the MOH Malaysia is increasing. The current global initiatives indicted that quality performance generally belong to three main categories: patient; staffing; and working environment related factors. There is no single intervention for optimizing quality of care to maintain patient safety. Multidimensional efforts and interventions are recommended in order to optimize the quality of care and patient safety in Malaysia.

  20. Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions

    Science.gov (United States)

    Jarrar, Mu’taman; Rahman, Hamzah Abdul; Don, Mohammad Sobri

    2016-01-01

    Background and Objective: Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Design: Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patient safety. The country health plan of Ministry of Health (MOH) Malaysia and the MOH Malaysia Annual Reports were reviewed. Results: The MOH has set four strategies for optimizing quality and sustaining quality of life. The 10th Malaysia Health Plan promotes the theme “1 Care for 1 Malaysia” in order to sustain the quality of care. Despite of these efforts, the total number of complaints received by the medico-legal section of the MOH Malaysia is increasing. The current global initiatives indicted that quality performance generally belong to three main categories: patient; staffing; and working environment related factors. Conclusions: There is no single intervention for optimizing quality of care to maintain patient safety. Multidimensional efforts and interventions are recommended in order to optimize the quality of care and patient safety in Malaysia. PMID:26755459

  1. The safety net medical home initiative: transforming care for vulnerable populations.

    Science.gov (United States)

    Sugarman, Jonathan R; Phillips, Kathryn E; Wagner, Edward H; Coleman, Katie; Abrams, Melinda K

    2014-11-01

    Despite findings that medical homes may reduce or eliminate health care disparities among underserved and minority populations, most previous medical home pilot and demonstration projects have focused on health care delivery systems serving commercially insured patients and Medicare beneficiaries. To develop a replicable approach to support medical home transformation among diverse practices serving vulnerable and underserved populations. Facilitated by a national program team, convening organizations in 5 states provided coaching and learning community support to safety net practices over a 4-year period. To guide transformation, we developed a framework of change concepts aligned with supporting tools including implementation guides, activity checklists, and measurement instruments. Sixty-five health centers, homeless clinics, private practices, residency training centers, and other safety net practices in Colorado, Idaho, Massachusetts, Oregon, and Pennsylvania. We evaluated implementation of the change concepts using the Patient-Centered Medical Home-Assessment, and conducted a survey of participating practices to assess perceptions of the impact of the technical assistance. All practices implemented key features of the medical home model, and nearly half (47.6%) implemented the 33 identified key changes to a substantial degree as evidenced by level A Patient-Centered Medical Home-Assessment scores. Two thirds of practices that achieved substantial implementation did so only after participating in the initiative for >2 years. By the end of the initiative, 83.1% of sites achieved external recognition as medical homes. Despite resource constraints and high-need populations, safety net clinics made considerable progress toward medical home implementation when provided robust, multimodal support over a 4-year period.

  2. Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions

    OpenAIRE

    Jarrar, Mu?taman; Rahman, Hamzah Abdul; Don, Mohammad Sobri

    2015-01-01

    Background and Objective: Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Design: Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patie...

  3. The Environmental Health/Home Safety Education Project: a successful and practical U.S.-Mexico border initiative.

    Science.gov (United States)

    Forster-Cox, Susan C; Mangadu, Thenral; Jacquez, Benjamín; Fullerton, Lynne

    2010-05-01

    The Environmental Health/Home Safety Education Project (Proyecto de Salud Ambiental y Seguridad en el Hogar) has been developed in response to a wide array of severe and often preventable environmental health issues occurring in and around homes on the U.S.-Mexico border. Utilizing well-trained community members, called promotoras , homes are visited and assessed for potential environmental hazards, including home fire and food safety issues. Data analyzed from project years 2002 to 2005 shows a significant impact in knowledge levels and initial behavior change among targeted participants as it relates to fire and food safety issues. Since the initiation of the project in 1999, hundreds of participants have improved their quality of life by making their homes safer. The project has proven to be sustainable, replicable, flexible, and attractive to funders.

  4. Initiation and arrest - two approaches to pressure vessel safety

    International Nuclear Information System (INIS)

    Brumovsky, M.; Filip, R.; Stepanek, S.

    1976-01-01

    The safety analysis is described of the reactor pressure vessel related to brittle fracture based on the fracture mechanics theory using two different approximations, i.e., the Crack Arrest Temperature (CAT) or Nil Ductility Temperature (NDT), and fracture toughness. The variation of CAT with stress was determined for different steel specimens of 120 to 200 mm in thickness. A diagram is shown of CAT variation with stress allowing the determination of crack arrest temperature for all types of commonly used steels independently of the NDT initial value. The diagram also shows that the difference between fracture transition elastic (FTE) and NDT depends on the type of material and determines the value of the ΔTsub(sigma) factor typical of the safety coefficient. The so-called fracture toughness reference value Ksub(IR) is recommended for the computation of pressure vessel criticality. Also shown is a defect analysis diagram which may be used for the calculation of pressure vessel safety prior to and during operation and which may also be used in making the decision on what crack sizes are critical, what cracks may be arrested and what cracks are likely to expand. The diagram is also important for the fact that it is material-independent and may be employed for the estimates of pre-operational and operational inspections and for pressure vessel life prediction. It is generally applicable to materials of greater thickness in the region where the validity of linear elastic fracture mechanics is guaranteed. (J.P.)

  5. Developing the Safety of Atrial Fibrillation Ablation Registry Initiative (SAFARI) as a collaborative pan-stakeholder critical path registry model: a Cardiac Safety Research Consortium "Incubator" Think Tank.

    Science.gov (United States)

    Al-Khatib, Sana M; Calkins, Hugh; Eloff, Benjamin C; Kowey, Peter; Hammill, Stephen C; Ellenbogen, Kenneth A; Marinac-Dabic, Danica; Waldo, Albert L; Brindis, Ralph G; Wilbur, David J; Jackman, Warren M; Yaross, Marcia S; Russo, Andrea M; Prystowsky, Eric; Varosy, Paul D; Gross, Thomas; Pinnow, Ellen; Turakhia, Mintu P; Krucoff, Mitchell W

    2010-10-01

    Although several randomized clinical trials have demonstrated the safety and efficacy of catheter ablation of atrial fibrillation (AF) in experienced centers, the outcomes of this procedure in routine clinical practice and in patients with persistent and long-standing persistent AF remain uncertain. Brisk adoption of this therapy by physicians with diverse training and experience highlights potential concerns regarding the safety and effectiveness of this procedure. Some of these concerns could be addressed by a national registry of AF ablation procedures such as the Safety of Atrial Fibrillation Ablation Registry Initiative that was initially proposed at a Cardiac Safety Research Consortium Think Tank meeting in April 2009. In January 2010, the Cardiac Safety Research Consortium, in collaboration with the Duke Clinical Research Institute, the US Food and Drug Administration, the American College of Cardiology, and the Heart Rhythm Society, held a follow-up meeting of experts in the field to review the construct and progress to date. Other participants included the National Heart, Lung, and Blood Institute; the Centers for Medicare and Medicaid Services; the Agency for Healthcare Research and Quality; the AdvaMed AF working group; and additional industry representatives. This article summarizes the discussions that occurred at the meeting of the state of the Safety of Atrial Fibrillation Ablation Registry Initiative, the identification of a clear pathway for its implementation, and the exploration of solutions to potential issues in the execution of this registry. Copyright © 2010 Mosby, Inc. All rights reserved.

  6. C-Band Airport Surface Communications System Engineering-Initial High-Level Safety Risk Assessment and Mitigation

    Science.gov (United States)

    Zelkin, Natalie; Henriksen, Stephen

    2011-01-01

    This document is being provided as part of ITT's NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract: "New ATM Requirements--Future Communications, C-Band and L-Band Communications Standard Development." ITT has completed a safety hazard analysis providing a preliminary safety assessment for the proposed C-band (5091- to 5150-MHz) airport surface communication system. The assessment was performed following the guidelines outlined in the Federal Aviation Administration Safety Risk Management Guidance for System Acquisitions document. The safety analysis did not identify any hazards with an unacceptable risk, though a number of hazards with a medium risk were documented. This effort represents an initial high-level safety hazard analysis and notes the triggers for risk reassessment. A detailed safety hazards analysis is recommended as a follow-on activity to assess particular components of the C-band communication system after the profile is finalized and system rollout timing is determined. A security risk assessment has been performed by NASA as a parallel activity. While safety analysis is concerned with a prevention of accidental errors and failures, the security threat analysis focuses on deliberate attacks. Both processes identify the events that affect operation of the system; and from a safety perspective the security threats may present safety risks.

  7. Enhancing the safety culture of non-power nuclear installations: Initiatives within the forum for nuclear cooperation in Asia

    International Nuclear Information System (INIS)

    Cameron, R.F.; Bastin, S.J.

    2002-01-01

    The development and application of safety culture principles has naturally focused on nuclear power plants and fuel cycle facilities and has been based on studies in Europe, North America, Japan and Korea. However, most radiation injuries and deaths have resulted from the mishandling of radioactive sources, inadvertent over-exposure to X-rays and criticality incidents, unrelated to nuclear power plant operations. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has promoted initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. The major focus has been on research reactors and to a lesser extent on fuel cycle facilities. The process has been motivated by annual workshops, where participants have reported against agreed indicators and shared their experiences in initiating safety culture programmes in these non-power nuclear activities. This paper provides a summary of some of the outcomes and conclusions on the effectiveness of these initiatives and some experiences from reviews of incidents in the participating countries. (author)

  8. FOCUS: the Society of Cardiovascular Anesthesiologists' initiative to improve quality and safety in the cardiovascular operating room.

    Science.gov (United States)

    Barbeito, Atilio; Lau, William Travis; Weitzel, Nathaen; Abernathy, James H; Wahr, Joyce; Mark, Jonathan B

    2014-10-01

    The Society of Cardiovascular Anesthesiologists (SCA) introduced the FOCUS initiative (Flawless Operative Cardiovascular Unified Systems) in 2005 in response to the need for a rigorous scientific approach to improve quality and safety in the cardiovascular operating room (CVOR). The goal of the project, which is supported by the SCA Foundation, is to identify hazards and develop evidence-based protocols to improve cardiac surgery safety. A hazard is anything that has the potential to cause a preventable adverse event. Specifically, the strategic plan of FOCUS includes 3 goals: (1) identifying hazards in the CVOR, (2) prioritizing hazards and developing risk-reduction interventions, and (3) disseminating these interventions. Collectively, the FOCUS initiative, through the work of several groups composed of members from different disciplines such as clinical medicine, human factors engineering, industrial psychology, and organizational sociology, has identified and documented significant hazards occurring daily in our CVORs. Some examples of frequent occurrences that contribute to reduce the safety and quality of care provided to cardiac surgery patients include deficiencies in teamwork, poor OR design, incompatible technologies, and failure to adhere to best practices. Several projects are currently under way that are aimed at better understanding these hazards and developing interventions to mitigate them. The SCA, through the FOCUS initiative, has begun this journey of science-driven improvement in quality and safety. There is a long and arduous road ahead, but one we need to continue to travel.

  9. A perinatal care quality and safety initiative: are there financial rewards for improved quality?

    Science.gov (United States)

    Kozhimannil, Katy B; Sommerness, Samantha A; Rauk, Phillip; Gams, Rebecca; Hirt, Charles; Davis, Stanley; Miller, Kristi K; Landers, Daniel V

    2013-08-01

    Although costs of providing care may decrease with hospital initiatives to improve obstetric and neonatal outcomes, the accompanying reduced adverse outcomes may negatively affect hospital revenues. In 2008 a Minnesota-based hospital system (Fairview Health Services) launched the Zero Birth Injury (ZBI) initiative, which used evidence-based care bundles to guide management of obstetric services. A pre-post analysis of financial impacts of ZBI was conducted by using hospital administrative records to measure costs and revenues associated with changes in maternal and neonatal birth injuries before (2008) and after (2009-2011) the initiative. For the Fairview Health Services hospitals, after adjusting for relevant covariates, implementation of ZBI was associated with a mean 11% decrease in the rate of maternal and neonatal adverse outcomes between 2008 and 2011 (adjusted odds ratio [AOR] = 0.89, p = .076). As a result of the adverse events avoided, the hospital system saved $284,985 in costs but earned $324,333 less revenue, which produced a net financial decrease of $39,348 (or a $305 net financial loss per adverse event avoided) in 2011, compared with 2008. Adoption of a perinatal quality and safety initiative that reduced birth injuries had little net financial impact on the hospital. ZBI produced better clinical results at a lower cost, which represents potential savings for payers, but the hospital system offering improved quality reaped no clear financial rewards. These results highlight the important role for shared-savings collaborations (among patients, providers, government and third-party payers, and employers) to incentivize QI. Widespread adoption of perinatal safety initiatives combined with innovative payment models may contribute to better health at reduced cost.

  10. Reactivity initiated accident analyses for the safety assessment of upgraded JRR-3

    International Nuclear Information System (INIS)

    Harami, Taikan; Uemura, Mutsumi; Ohnishi, Nobuaki

    1984-08-01

    JRR-3, currently a heavy water moderated and cooled 10 MW reactor, is to be upgraded to a light water moderated and cooled, heavy water reflected 20 MW reactor. This report describes the analytical results of reactivity initiated accidents for the safety assessment of upgraded JRR-3. The following five cases have been selected for the assessment; (1) uncontrolled control rod withdrawal from zero power, (2) uncontrolled control rod withdrawal from full power, (3) removal of irradiation samples, (4) increase of primary coolant flow, (5) failure of heavy water tank. Parameter studies have been made for each of the above cases to cover possible uncertainties. All analyses have been made by a computer code EUREKA-2. The results show that the safety criteria for upgraded JRR-3 are all met and the adequacy of the design is confirmed. (author)

  11. Safety and Security of Radioactive Sources: Initiatives of the Forum of Nuclear Regulatory Bodies in Africa (FNRBA)

    International Nuclear Information System (INIS)

    Severa, R.

    2010-01-01

    Safety and Security of Radioactive Sources: Initiatives of the Forum of Nuclear Regulatory Bodies in Africa(FNRBA) is a regional organization comprising of nuclear regulatory bodies it’s goals are to promote the establishment of regulatory infrastructure in all countries of the Region to adopt joint action plan for implementation of self-assessment and work with Member States to upgrade their regulatory infrastructures, develop and promote a framework for capacity building in areas of radiation and nuclear safety and security, to create an opportunity for mutual support and coordination of regional initiatives by leveraging the development and utilization of regional and international resources and expertise and to serve as reference body on matters relating to nuclear and radiation safety and security in the Region. Radioactive active sources continue to play an increasingly important role in socio-economic activities on the African continent. There is also an ever increasing need to ensure that radioactive sources are utilized in a safe and secure manner

  12. Companies' opinions and acceptance of global food safety initiative benchmarks after implementation.

    Science.gov (United States)

    Crandall, Phil; Van Loo, Ellen J; O'Bryan, Corliss A; Mauromoustakos, Andy; Yiannas, Frank; Dyenson, Natalie; Berdnik, Irina

    2012-09-01

    International attention has been focused on minimizing costs that may unnecessarily raise food prices. One important aspect to consider is the redundant and overlapping costs of food safety audits. The Global Food Safety Initiative (GFSI) has devised benchmarked schemes based on existing international food safety standards for use as a unifying standard accepted by many retailers. The present study was conducted to evaluate the impact of the decision made by Walmart Stores (Bentonville, AR) to require their suppliers to become GFSI compliant. An online survey of 174 retail suppliers was conducted to assess food suppliers' opinions of this requirement and the benefits suppliers realized when they transitioned from their previous food safety systems. The most common reason for becoming GFSI compliant was to meet customers' requirements; thus, supplier implementation of the GFSI standards was not entirely voluntary. Other reasons given for compliance were enhancing food safety and remaining competitive. About 54 % of food processing plants using GFSI benchmarked schemes followed the guidelines of Safe Quality Food 2000 and 37 % followed those of the British Retail Consortium. At the supplier level, 58 % followed Safe Quality Food 2000 and 31 % followed the British Retail Consortium. Respondents reported that the certification process took about 10 months. The most common reason for selecting a certain GFSI benchmarked scheme was because it was widely accepted by customers (retailers). Four other common reasons were (i) the standard has a good reputation in the industry, (ii) the standard was recommended by others, (iii) the standard is most often used in the industry, and (iv) the standard was required by one of their customers. Most suppliers agreed that increased safety of their products was required to comply with GFSI benchmarked schemes. They also agreed that the GFSI required a more carefully documented food safety management system, which often required

  13. Leveraging the Partnership for Patients' Initiative to Improve Patient Safety and Quality Within the Military Health System.

    Science.gov (United States)

    King, Heidi B; Kesling, Kimberly; Birk, Carmen; Walker, Theodore; Taylor, Heather; Datena, Michael; Burgess, Brittany; Bower, Lyndsay

    2017-03-01

    Partnership for Patients (PfP) was a national initiative sponsored by the Department of Health and Human Services, Centers for Medicare and Medicaid Services, to reduce preventable hospital acquired conditions (HACs) by 40% and readmissions (within 30 days) by 20%, by the end of 2013 (as compared to the baseline of CY2010). Along with partners across the nation, the Assistant Secretary of Defense for Health Affairs, Dr. Jonathan Woodson, pledged to support PfP in June 2011. Participation of the Military Health System (MHS) in PfP marked the implementation of the first enterprise-wide patient safety initiative. Three phases of the MHS initiative were developed to meet the aims of the national PfP initiative: (1) Planning and Design, (2) Implementation, and (3) Monitoring and Sustainment. The Planning and Design phase focused on the identification of evidence-based practices (Table III); the development of implementation guides; the implementation of various communication, education, and improvement strategies; and the development of methods by which to track progress and share successes. The implementation phase focused on identifying roles and responsibilities across all levels of care; creating, disseminating, and implementing evidence-based practices at participating military treatment facilities; and establishing a structured learning action network. Finally, during the monitoring and sustainment phase, per the guidance of the Agency for Healthcare Research and Quality, an overall HAC rate was developed for quarterly analysis. The HAC rate per 1,000 dispositions (i.e., discharges) was an aggregate of all PfP HACs. Using the HAC rate, the improvement rate was calculated by comparing the current quarter's HAC rate to the baseline (CY2010). This allowed the MHS to track the overall progress across the enterprise. The MHS achieved a number of accomplishments, including a 15.8% cumulative reduction in HACs by the end of 2013, an 11.1% reduction in readmissions

  14. Breckinridge Project, initial effort. Report VII, Volume 4. Safety and health plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The Safety and Health Plan recognizes the potential hazards associated with the Project and has been developed specifically to respond to these risks in a positive manner. Prevention, the primary objective of the Plan, starts with building safety controls into the process design and continues through engineering, construction, start-up, and operation of the Project facilities and equipment. Compliance with applicable federal, state, and local health and safety laws, regulations, and codes throughout all Project phases is required and assured. The Plan requires that each major Project phase be thoroughly reviewed and analyzed to determine that those provisions required to assure the safety and health of all employees and the public, and to prevent property and equipment losses, have been provided. The Plan requires followup on those items or situations where corrective action needs were identified to assure that the action was taken and is effective. Emphasis is placed on loss prevention. Exhibit 1 provides a breakdown of Ashland Synthetic Fuels, Inc.'s (ASFI's) Loss Prevention Program. The Plan recognizes that the varied nature of the work is such as to require the services of skilled, trained, and responsible personnel who are aware of the hazards and know that the work can be done safely, if done correctly. Good operating practice is likewise safe operating practice. Training is provided to familiarize personnel with good operational practice, the general sequence of activities, reporting requirements, and above all, the concept that each step in the operating procedures must be successfully concluded before the following step can be safely initiated. The Plan provides for periodic review and evaluation of all safety and loss prevention activities at the plant and departmental levels.

  15. Safety of fentanyl initiation according to past opioid exposure among patients newly prescribed fentanyl patches

    Science.gov (United States)

    Friesen, Kevin J.; Woelk, Cornelius; Bugden, Shawn

    2016-01-01

    Background: Although a convenient opioid delivery system, transdermal fentanyl patches have caused several deaths and resulted in safety warnings reminding prescribers that fentanyl patches should be prescribed only for patients who have adequate prior exposure to opioids. We conducted a longitudinal analysis of the safety of fentanyl initiation by examining past opioid exposure among patients newly prescribed fentanyl patches. Methods: We identified all patients in the province of Manitoba who were newly prescribed fentanyl patches between Apr. 1, 2001, and Mar. 31, 2013. We converted all prior opioid use to oral morphine equivalents and determined the average daily dose in the 7–30 days before initial fentanyl patch use. Fentanyl initiation was considered unsafe if the patient’s pre-fentanyl opioid exposure was below the recommended level. Results: We identified 11 063 patients who began using fentanyl patches during the study period. Overall, fentanyl initiation was deemed unsafe in 74.1% of cases because the patient’s prior opioid exposure was inadequate. Women and patients 65 years of age and older were more likely than men and younger patients, respectively, to have inadequate prior opioid exposure (p fentanyl patches decreased significantly over the study period, from 87.0% in 2001 to 50.0% in 2012 (p fentanyl initiation improved over the study period, but still half of fentanyl patch prescriptions were written for patients with inadequate prior opioid exposure. Review of prior opioid exposure may be a simple but important way to improve the safe use of fentanyl patches. PMID:27044480

  16. The West Virginia Occupational Safety and Health Initiative: practicum training for a new marketplace.

    Science.gov (United States)

    Meyer, J D; Becker, P E; Stockdale, T; Ducatman, A M

    1999-05-01

    Occupational medicine practice has experienced a shift from larger corporate medical departments to organizations providing services for a variety of industries. Specific training needs will accompany this shift in practice patterns; these may differ from those developed in the traditional industrial or corporate medical department setting. The West Virginia Occupational Health and Safety Initiative involves occupational medicine residents in consultation to a variety of small industries and businesses. It uses the expertise of occupational physicians, health and safety extension faculty, and faculty in engineering and industrial hygiene. Residents participate in multidisciplinary evaluations of worksites, and develop competencies in team-building, workplace health and safety evaluation, and occupational medical consulting. Specific competencies that address requirements for practicum training are used to measure the trainee's acquisition of knowledge and skills. Particular attention is paid to the acquisition of group problem-solving expertise, skills relevant to the current market in practice opportunities, and the specific career interests of the resident physician. Preliminary evaluation indicates the usefulness of training in evaluation of diverse industries and worksites. We offer this program as a training model that can prepare residents for the challenges of a changing marketplace for occupational health and safety services.

  17. A consistent approach to assess safety criteria for reactivity initiated accidents

    International Nuclear Information System (INIS)

    Sartoris, C.; Taisne, A.; Petit, M.; Barre, F.; Marchand, O.

    2010-01-01

    In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up increases and raises the question of the current safety criteria relevance. In order to assess new safety criteria for reactivity initiated accidents, the IRSN is developing a consistent and original approach to assess safety. This approach is based on: -A thorough understanding of the physical mechanisms involved in each phase (PCMI and post-boiling phases) of the RIA, supported by the interpretation of the experimental database. This experimental data is constituted of global test outcomes, such as CABRI or Nuclear Safety Research Reactor (NSRR) experiments, and analytical program outcomes, such as PATRICIA tests, intending to understand some particular physical phenomena; -The development of computing codes, modelling the physical phenomena. The physical phenomena observed during the tests mentioned above were modelled in the SCANAIR code. SCANAIR is a thermal-mechanical code calculating fuel and clad temperatures and strains during RIA. The CLARIS module is used as a post-calculation tool to evaluate the clad failure risk based on critical flaw depth. These computing codes were validated by global and analytical tests results; -The development of a methodology. The first step of this methodology is the identification of all the parameters affecting the hydride rim depth. Besides, an envelope curve resulting from burst tests giving the hydride rim depth versus oxidation thickness is defined. After that, the critical flaw depth for a given energy pulse is calculated then compared to the hydride rim depth. This methodology results in an energy or enthalpy limit versus burn-up. This approach is planned to be followed for each phase of the RIA. An example of application is presented to evaluate a PCMI limit for a zircaloy-4 cladding UO 2 rod at Hot Zero Power.

  18. Dicty_cDB: SHB534 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available s) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 99 2e-19... BC138482_1( BC138482 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 97 6e-19 (Q9JLC8) RecName: Full=Sacsi

  19. Impact of the Global Food Safety Initiative on Food Safety Worldwide: Statistical Analysis of a Survey of International Food Processors.

    Science.gov (United States)

    Crandall, Philip G; Mauromoustakos, Andy; O'Bryan, Corliss A; Thompson, Kevin C; Yiannas, Frank; Bridges, Kerry; Francois, Catherine

    2017-10-01

    In 2000, the Consumer Goods Forum established the Global Food Safety Initiative (GFSI) to increase the safety of the world's food supply and to harmonize food safety regulations worldwide. In 2013, a university research team in conjunction with Diversey Consulting (Sealed Air), the Consumer Goods Forum, and officers of GFSI solicited input from more than 15,000 GFSI-certified food producers worldwide to determine whether GFSI certification had lived up to these expectations. A total of 828 usable questionnaires were analyzed, representing about 2,300 food manufacturing facilities and food suppliers in 21 countries, mainly across Western Europe, Australia, New Zealand, and North America. Nearly 90% of these certified suppliers perceived GFSI as being beneficial for addressing their food safety concerns, and respondents were eight times more likely to repeat the certification process knowing what it entailed. Nearly three-quarters (74%) of these food manufacturers would choose to go through the certification process again even if certification were not required by one of their current retail customers. Important drivers for becoming GFSI certified included continuing to do business with an existing customer, starting to do business with new customer, reducing the number of third-party food safety audits, and continuing improvement of their food safety program. Although 50% or fewer respondents stated that they saw actual increases in sales, customers, suppliers, or employees, significantly more companies agreed than disagreed that there was an increase in these key performance indicators in the year following GFSI certification. A majority of respondents (81%) agreed that there was a substantial investment in staff time since certification, and 50% agreed there was a significant capital investment. This survey is the largest and most representative of global food manufacturers conducted to date.

  20. Are area-based initiatives able to improve area safety in deprived areas? A quasi-experimental evaluation of the Dutch District Approach.

    Science.gov (United States)

    Kramer, Daniëlle; Jongeneel-Grimen, Birthe; Stronks, Karien; Droomers, Mariël; Kunst, Anton E

    2015-07-28

    Numerous area-based initiatives have been implemented in deprived areas across Western-Europe with the aim to improve the socio-economic and environmental conditions in these areas. Only few of these initiatives have been scientifically evaluated for their impact on key social determinants of health, like perceived area safety. Therefore, this study aimed to assess the impact of a Dutch area-based initiative called the District Approach on trends in perceived area safety and underlying problems in deprived target districts. A quasi-experimental design was used. Repeated cross-sectional data on perceived area safety and underlying problems were obtained from the National Safety Monitor (2005-2008) and its successor the Integrated Safety Monitor (2008-2011). Study population consisted of 133,522 Dutch adults, including 3,595 adults from target districts. Multilevel logistic regression analyses were performed to assess trends in self-reported general safety, physical order, social order, and non-victimization before and after the start of the District Approach mid-2008. Trends in target districts were compared with trends in various control groups. Residents of target districts felt less safe, perceived less physical and social order, and were victimized more often than adults elsewhere in the Netherlands. For non-victimization, target districts showed a somewhat more positive change in trend after the start of the District Approach than the rest of the Netherlands or other deprived districts. Differences were only statistically significant in women, older adults, and lower educated adults. For general safety, physical order, and social order, there were no differences in trend change between target districts and control groups. Results suggest that the District Approach has been unable to improve perceptions of area safety and disorder in deprived areas, but that it did result in declining victimization rates.

  1. Risk management in a humanitarian context - how can the application of risk management activities to initial registration in Dadaab increase societal safety?

    OpenAIRE

    Nodland, Jeanneth

    2011-01-01

    Master's thesis in Risk management and societal safety The aim of this thesis is to establish the relationship between initial registration and societal safety, to make the reader aware of how the UNHCR in Dadaab is conducting initial registration, and to show that the application of risk management activities on camp management activities can increase the reliability of an operation. The thesis will show that the identification of vulnerabilities embedded within a system, and implementing...

  2. AcEST: DK944957 [AcEST

    Lifescience Database Archive (English)

    Full Text Available ant alignments: (bits) Value sp|Q82Y15|ORN_NITEU Oligoribonuclease OS=Nitrosomonas europaea G... 31 1.7 sp|Q9JLC8|SACS_MOUSE Sacsi...LVVTDAQLNTLAEAPVLVVHQPDDI 54 >sp|Q9JLC8|SACS_MOUSE Sacsin OS=Mus musculus GN=Sacs PE=1 SV=2 Length = 4582 Sc

  3. Safety, safety case and society - Lessons from the experience of the Forum on Stakeholder Confidence and other NEA initiatives

    International Nuclear Information System (INIS)

    Pescatore, Claudio

    2014-01-01

    A vast amount of literature on radioactive waste management (RWM) and its governance is available on the web page of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA), in particular on the pages of the Forum on Stakeholder Confidence (FSC), the Reversibility and Retrievability (R and R) Project and the Project on Records, Knowledge and Memory (RK and M) Preservation across Generations. The FSC literature alone likely represents the largest collection of literature on RWM governance presently available on any single site. The safety case developed for any deep geological repository project deals with technical safety. A license is to be granted based on the repository being, after closure, safe 'by itself', i.e. without the need to watch it, independent of the existence of the implementer, regulator and others. The main legal requirement of the safety case is that it needs to show convincingly that the technical regulatory criteria are met. The latter are both qualitative and quantitative. Qualitative criteria are technical, but not in a strong sense, e.g. one requirement may simply be the use of 'sound technical and managerial principles'. The safety case also needs to argue robustness upon human intrusion. The human intrusion analyses, however, are only used to make a qualitative judgement on the robustness of the system. The international guidance suggests that their results need not be tested, by the authorities, for compliance against a numerical yardstick. The technical regulator will have an important role in decision making, but others aside from the technical regulator will also play a decision-making role in the development of a repository project and with regard to its safety. For instance, the technical regulator is largely removed from the initial choice of site. Safety nowadays is brought about by a system of actors comprising the implementer, technical regulators, specialist groups in various advisory roles and the

  4. A Strategic Approach for Funding Research: The Agency for Healthcare Research and Quality's Patient Safety Initiative 2000-2004

    National Research Council Canada - National Science Library

    Keyes, Margaret A; Ortiz, Eduardo; Queenan, Deborah; Hughes, Ronda; Chesley, Francis; Hogan, Eileen M

    2005-01-01

    .... While the Agency for Healthcare Research and Quality (AHRQ) has historically funded some research on patient safety, much of that support was driven by a small number of highquality investigator-initiated research projects...

  5. Quantification of the impact of multifaceted initiatives intended to improve operational efficiency and the safety culture: a case study from an academic medical center radiation oncology department.

    Science.gov (United States)

    Chera, Bhishamjit S; Mazur, Lukasz; Jackson, Marianne; Taylor, Kinely; Mosaly, Prithima; Chang, Sha; Deschesne, Kathy; LaChapelle, Dana; Hoyle, Lesley; Saponaro, Patricia; Rockwell, John; Adams, Robert; Marks, Lawrence B

    2014-01-01

    We have systematically been incorporating several operational efficiency and safety initiatives into our academic radiation oncology clinic. We herein quantify the impact of these initiatives on prospectively collected, clinically meaningful, metrics. The data from 5 quality improvement initiatives, each focused on a specific safety/process concern in our clinic, are presented. Data was collected prospectively: operational metrics recorded before and after implementation of the initiative were compared using statistical analysis. Results from the Agency for Health Care Research and Quality (AHRQ) patient safety culture surveys administered during and after many of these initiatives were similarly compared. (1) Workload levels for nurses assisting with brachytherapy were high (National Aeronautics and Space Administration Task Load Index (NASA-TLX) scores >55-60, suggesting, "overwork"). Changes in work flow and procedure room layout reduced workload to more acceptable levels (NASA-TLX 50% to <10%; P < .01). To assess the overall changes in "patient safety culture," we conducted a pre- and postanalysis using the AHRQ survey. Improvements in all measured dimensions were noted. Quality improvement initiatives can be successfully implemented in an academic radiation oncology department to yield measurable improvements in operations resulting in improvement in patient safety culture. Copyright © 2014 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  6. Dicty_cDB: SHI292 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available nt alignments: (bits) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 106 4e-22 BC1384...82_1( BC138482 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 104 2e-21 (Q9JLC8) RecName: Full=Sacsi

  7. Clinical Trial Electronic Portals for Expedited Safety Reporting: Recommendations from the Clinical Trials Transformation Initiative Investigational New Drug Safety Advancement Project.

    Science.gov (United States)

    Perez, Raymond P; Finnigan, Shanda; Patel, Krupa; Whitney, Shanell; Forrest, Annemarie

    2016-12-15

    Use of electronic clinical trial portals has increased in recent years to assist with sponsor-investigator communication, safety reporting, and clinical trial management. Electronic portals can help reduce time and costs associated with processing paperwork and add security measures; however, there is a lack of information on clinical trial investigative staff's perceived challenges and benefits of using portals. The Clinical Trials Transformation Initiative (CTTI) sought to (1) identify challenges to investigator receipt and management of investigational new drug (IND) safety reports at oncologic investigative sites and coordinating centers and (2) facilitate adoption of best practices for communicating and managing IND safety reports using electronic portals. CTTI, a public-private partnership to improve the conduct of clinical trials, distributed surveys and conducted interviews in an opinion-gathering effort to record investigator and research staff views on electronic portals in the context of the new safety reporting requirements described in the US Food and Drug Administration's final rule (Code of Federal Regulations Title 21 Section 312). The project focused on receipt, management, and review of safety reports as opposed to the reporting of adverse events. The top challenge investigators and staff identified in using individual sponsor portals was remembering several complex individual passwords to access each site. Also, certain tasks are time-consuming (eg, downloading reports) due to slow sites or difficulties associated with particular operating systems or software. To improve user experiences, respondents suggested that portals function independently of browsers and operating systems, have intuitive interfaces with easy navigation, and incorporate additional features that would allow users to filter, search, and batch safety reports. Results indicate that an ideal system for sharing expedited IND safety information is through a central portal used by

  8. Patient safety: Safety culture and patient safety ethics

    DEFF Research Database (Denmark)

    Madsen, Marlene Dyrløv

    2006-01-01

    ,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

  9. Probabilistic safety analysis on an SBWR 72 hours after the initiating event

    International Nuclear Information System (INIS)

    Dominguez Bautista, M.T.; Peinador Veira, M.

    1996-01-01

    Passive plants, including SBWRs, are designed to carry out safety functions with passive systems during the first 72 hours after the initiation event with no need for manual actions or external support. After this period, some recovery actions are required to enable the passive systems to continue performing their safety functions. The study was carried out by the INITEC-Empresarios Agrupados Joint Venture within the framework of the international group collaborating with GE on this project. Its purpose has been to assess, by means of probabilistic criteria, the importance to safety of each of these support actions, in order to define possible requirements to be considered in the design in respect of said recovery actions. In brief, the methodology developed for this objective consists of (1) quantifying success event trees from the PSA up to 72 hours, (2) determining the actions required in each sequence to maintain Steady State after 72 hours, (3) identifying available alternative core cooling methods in each sequence, (4) establishing the approximate (order of magnitude) realizability of each alternative method, (5) calculating the frequency of core damage as a function of the failure probability of post-72-hour actions and (6) analysing the importance of post-72-hour actions. The results of this analysis permit the establishment, right from the conceptual design phase, of the requirements that will arise to ensure these actions in the long term, enhancing their reliability and preventing the accident from continuing beyond this period. (Author)

  10. ELECTRICAL SAFETY IMPROVEMENT PROJECT A COMPLEX WIDE TEAMING INITIATIVE

    Energy Technology Data Exchange (ETDEWEB)

    GRAY BJ

    2007-11-26

    This paper describes the results of a year-long project, sponsored by the Energy Facility Contractors Group (EFCOG) and designed to improve overall electrical safety performance throughout Department of Energy (DOE)-owned sites and laboratories. As evidenced by focused metrics, the Project was successful primarily due to the joint commitment of contractor and DOE electrical safety experts, as well as significant support from DOE and contractor senior management. The effort was managed by an assigned project manager, using classical project-management principles that included execution of key deliverables and regular status reports to the Project sponsor. At the conclusion of the Project, the DOE not only realized measurable improvement in the safety of their workers, but also had access to valuable resources that will enable them to do the following: evaluate and improve electrical safety programs; analyze and trend electrical safety events; increase electrical safety awareness for both electrical and non-electrical workers; and participate in ongoing processes dedicated to continued improvement.

  11. Efficacy of a radiation safety education initiative in reducing radiation exposure in the pediatric IR suite

    International Nuclear Information System (INIS)

    Sheyn, David D.; Racadio, John M.; Patel, Manish N.; Racadio, Judy M.; Johnson, Neil D.; Ying, Jun

    2008-01-01

    The use of ionizing radiation is essential for diagnostic and therapeutic imaging in the interventional radiology (IR) suite. As the complexity of procedures increases, radiation exposure risk increases. We believed that reinforcing staff education and awareness would help optimize radiation safety. To evaluate the effect of a radiation safety education initiative on IR staff radiation safety practices and patient radiation exposure. After each fluoroscopic procedure performed in the IR suite during a 4-month period, dose-area product (DAP), fluoroscopy time, and use of shielding equipment (leaded eyeglasses and hanging lead shield) by IR physicians were recorded. A lecture and article were then given to IR physicians and technologists that reviewed ALARA principles for optimizing radiation dose. During the following 4 months, those same parameters were recorded after each procedure. Before education 432 procedures were performed and after education 616 procedures were performed. Physician use of leaded eyeglasses and hanging shield increased significantly after education. DAP and fluoroscopy time decreased significantly for uncomplicated peripherally inserted central catheters (PICC) procedures and non-PICC procedures after education, but did not change for complicated PICC procedures. Staff radiation safety education can improve IR radiation safety practices and thus decrease exposure to radiation of both staff and patients. (orig.)

  12. Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents

    Energy Technology Data Exchange (ETDEWEB)

    Ovdiienko, Iurii; Bilodid, Yevgen; Ieremenko, Maksym [State Scientific and Technical Centre on Nuclear and Radiation, Safety (SSTC N and RS), Kyiv (Ukraine); Loetsch, Thomas [TUEV SUED Industrie Service GmbH, Energie und Systeme, Muenchen (Germany)

    2016-09-15

    At present time, Ukraine faces the problem of small margins of acceptance criteria in connection with the implementation of a conservative approach for safety evaluations. The problem is particularly topical conducting feasibility analysis of power up-rating for Ukrainian nuclear power plants. Such situation requires the implementation of a best-estimate approach on the basis of an uncertainty analysis. For some kind of accidents, such as loss-of-coolant accident (LOCA), the best estimate approach is, more or less, developed and established. However, for reactivity initiated accident (RIA) analysis an application of best estimate method could be problematical. A regulatory document in Ukraine defines a nomenclature of neutronics calculations and so called ''generic safety parameters'' which should be used as boundary conditions for all VVER-1000 (V-320) reactors in RIA analysis. In this paper the ideas of uncertainty evaluations of generic safety parameters in RIA analysis in connection with the use of the 3D neutron kinetic code DYN3D and the GRS SUSA approach are presented.

  13. The French-German initiative for Chernobyl. Programme 1 safety state of the sarcophagus

    Energy Technology Data Exchange (ETDEWEB)

    Pretzsch, G.; Roloff, R.; Roloff, R.; Artmann, A. [Gesellschaft fur Anlagenund Reaktorsicherheit (GRS) (Germany); Lhomme, V. [Institut de Radioprotection et de Surete Nucleaire, 92 - Fontenay-aux-Roses (France); Berberich, G. [Erftstadt-Gymnich (Germany); Selesnew, A

    2005-07-01

    The data collected and processed within the framework of the French-German Initiative are an excellent basis for the intended specialist application at the Chernobyl Centre as well as for an extended use in connection with the restoration of the Sarcophagus as part of the 'Shelter Implementation Plan' performed under the auspices of the European Bank for Reconstruction and Development. The major goals of the S.I.P. are the stabilisation of the existing Sarcophagus and the erection of a New Safe Confinement (N.S.C.) around the already existing Sarcophagus, the degasifier wing and the turbine building.This N.S.C. is to safely confine the radioactive materials for at least 100 years and is to allow their retrieval from inside if need be as well as the dismantling of the old structure.In addition, the database can be used for obtaining information needed for project descriptions, safety analysis reports, etc. The Ukrainian safety authority S.N.R.C.U. (State Nuclear Regulatory Committee of Ukraine) and its technical safety organisation, the State Scientific-Technical Center (S.S.T.C.), have also signaled their interest in using the database.Further information on the F.G.I. and on the 'Radioecology and Health Programmes' can be found at: www.fgi1-chernobyl.de.vu; www.grs.de, www.irsn.fr; www.fgi.icc.gov.ua. (N.C.)

  14. Leadership, safety climate, and continuous quality improvement: impact on process quality and patient safety.

    Science.gov (United States)

    McFadden, Kathleen L; Stock, Gregory N; Gowen, Charles R

    2014-10-01

    Successful amelioration of medical errors represents a significant problem in the health care industry. There is a need for greater understanding of the factors that lead to improved process quality and patient safety outcomes in hospitals. We present a research model that shows how transformational leadership, safety climate, and continuous quality improvement (CQI) initiatives are related to objective quality and patient safety outcome measures. The proposed framework is tested using structural equation modeling, based on data collected for 204 hospitals, and supplemented with objective outcome data from the Centers for Medicare and Medicaid Services. The results provide empirical evidence that a safety climate, which is connected to the chief executive officer's transformational leadership style, is related to CQI initiatives, which are linked to improved process quality. A unique finding of this study is that, although CQI initiatives are positively associated with improved process quality, they are also associated with higher hospital-acquired condition rates, a measure of patient safety. Likewise, safety climate is directly related to improved patient safety outcomes. The notion that patient safety climate and CQI initiatives are not interchangeable or universally beneficial is an important contribution to the literature. The results confirm the importance of using CQI to effectively enhance process quality in hospitals, and patient safety climate to improve patient safety outcomes. The overall pattern of findings suggests that simultaneous implementation of CQI initiatives and patient safety climate produces greater combined benefits.

  15. Preliminary safety evaluation, based on initial site investigation data. Planning document

    International Nuclear Information System (INIS)

    Hedin, Allan

    2002-12-01

    This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C

  16. Development and initial validation of an Aviation Safety Climate Scale.

    Science.gov (United States)

    Evans, Bronwyn; Glendon, A Ian; Creed, Peter A

    2007-01-01

    A need was identified for a consistent set of safety climate factors to provide a basis for aviation industry benchmarking. Six broad safety climate themes were identified from the literature and consultations with industry safety experts. Items representing each of the themes were prepared and administered to 940 Australian commercial pilots. Data from half of the sample (N=468) were used in an exploratory factor analysis that produced a 3-factor model of Management commitment and communication, Safety training and equipment, and Maintenance. A confirmatory factor analysis on the remaining half of the sample showed the 3-factor model to be an adequate fit to the data. The results of this study have produced a scale of safety climate for aviation that is both reliable and valid. This study developed a tool to assess the level of perceived safety climate, specifically of pilots, but may also, with minor modifications, be used to assess other groups' perceptions of safety climate.

  17. Assessment of Patient Safety Friendly Hospital Initiative in Three Hospitals Affiliated to Tehran University of Medical Sciences

    Directory of Open Access Journals (Sweden)

    Firoozeh Bairami

    2016-01-01

    Full Text Available Introduction: The aim of this study was to assess the status of patient safety in three hospitals, affiliated to Tehran University of Medical Sciences, based on the critical standards of Patient Safety Friendly Hospital Initiative (PSFHI. Materials and Methods:In this cross-sectional study, conducted in 2014, we used PSFHI assessment tool to evaluate the status of patient safety in three hospitals, affiliated to Tehran University of Medical Sciences; these general referral hospitals were selected purposefully. PSFHI assessment tool is comprised of 140 patient safety standards in five domains, categorized in 24 sub-domains. The five major domains include leadership and management, patient and public involvement, safe evidence-based clinical practices, safe environment, and lifelong learning. Results: All three hospitals met more than 70% of the critical standards. The highest score in critical standards (> 80% was related to the domain of leadership and management in all hospitals. The average score in the domain of safe evidence-based clinical practices was 70% in the studied hospitals. Finally, all the hospitals met 50% of the critical standards in the domains of patient and public involvement and safe environment. Conclusion: Based on the findings, PSFHI is a suitable program for meeting patient safety goals. The selected hospitals in this survey all had a high managerial commitment to patient safety; therefore, they could obtain high scores on critical standards.

  18. How safe is the safety paradigm?

    NARCIS (Netherlands)

    O.A. Arah (Onyebuchi); N.S. Klazinga (Niek)

    2004-01-01

    textabstractThis paper reviews safety initiatives in the health systems of the UK, Canada, Australia, and the US. Initiatives to tackle safety shortcomings involve public-private collaborations. Patient safety agencies (to institute learning, action and safety culture), adverse

  19. The design of infrared laser radar for vehicle initiative safety

    Science.gov (United States)

    Gong, Ping; Xu, Xi-ping; Li, Xiao-yu; Li, Tian-zhi; Liu, Yu-long; Wu, Jia-hui

    2013-09-01

    Laser radar for vehicle is mainly used in advanced vehicle on-board active safety systems, such as forward anti-collision systems, active collision warning systems and adaptive cruise control systems, etc. Laser radar for vehicle plays an important role in the improvement of vehicle active safety and the reduction of traffic accidents. The stability of vehicle active anti-collision system in dynamic environment is still one of the most difficult problems to break through nowadays. According to people's driving habit and the existed detecting technique of sensor, combining the infrared laser range and galvanometer scanning technique , design a 3-D infrared laser radar which can be used to assist navigation, obstacle avoidance and the vehicle's speed control for the vehicle initiative safety. The device is fixed to the head of vehicle. Then if an accident happened, the device could give an alarm to remind the driver timely to decelerate or brake down, by which way can people get the purpose of preventing the collision accidents effectively. To accomplish the design, first of all, select the core components. Then apply Zemax to design the transmitting and receiving optical system. Adopt 1550 nm infrared laser transmitter as emission unit in the device, a galvanometer scanning as laser scanning unit and an InGaAs-APD detector as laser echo signal receiving unit. Perform the construction of experimental system using FPGA and ARM as the core controller. The system designed in this paper can not only detect obstacle in front of the vehicle and make the control subsystem to execute command, but also transfer laser data to PC in real time. Lots of experiments using the infrared laser radar prototype are made, and main performance of it is under tested. The results of these experiments show that the imaging speed of the laser radar can reach up to 25 frames per second, the frame resolution of each image can reach 30×30 pixels, the horizontal angle resolution is about 6. 98

  20. How safe is the safety paradigm?

    NARCIS (Netherlands)

    Arah, O. A.; Klazinga, N. S.

    2004-01-01

    This paper reviews safety initiatives in the health systems of the UK, Canada, Australia, and the US. Initiatives to tackle safety shortcomings involve public-private collaborations. Patient safety agencies (to institute learning, action and safety culture), adverse event reporting and, to a lesser

  1. Integrated Initiating Event Performance Indicators

    International Nuclear Information System (INIS)

    S. A. Eide; Dale M. Rasmuson; Corwin L. Atwood

    2005-01-01

    The U.S. Nuclear Regulatory Commission Industry Trends Program (ITP) collects and analyses industry-wide data, assesses the safety significance of results, and communicates results to Congress and other stakeholders. This paper outlines potential enhancements in the ITP to comprehensively cover the Initiating Events Cornerstone of Safety. Future work will address other cornerstones of safety. The proposed Tier 1 activity involves collecting data on ten categories of risk-significant initiating events, trending the results, and comparing early performance with prediction limits (allowable numbers of events, above which NRC action may occur). Tier 1 results would be used to monitor industry performance at the level of individual categories of initiating events. The proposed Tier 2 activity involves integrating the information for individual categories of initiating events into a single risk-based indicator, termed the Baseline Risk Index for Initiating Events or BRIIE. The BRIIE would be evaluated yearly and compared against a threshold. BRIIE results would be reported to Congress on a yearly basis

  2. Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA Reactor

    International Nuclear Information System (INIS)

    Maskin, M.; Charlie, F.; Hassan, A.; Prak Tom, P.; Ramli, Z.; Mohamed, F.

    2016-01-01

    Highlights: • Identifying possible important initiating events (IEs) for Level 1 probabilistic safety assessment performed on research nuclear reactor. • Methods in screening and grouping IEs are addressed. • Focusing only on internal IEs due to random failures of components. - Abstract: This paper attempts to present the results in identifying possible important initiating events (IEs) as comprehensive as possible to be applied in the development of Level-1 probabilistic safety assessment (PSA) study. This involves the approaches in listing and the methods in screening and grouping IEs, by focusing only on the internal IEs due to random failures of components and human errors with full power operational conditions and reactor core as the radioactivity source. Five approaches were applied in listing the IEs and each step of the methodology was described and commented. The criteria in screening and grouping the IEs were also presented. The results provided the information on how the Malaysian PSA team applied the approaches in selecting the most probable IEs as complete as possible in order to ensure the set of IEs was identified systematically and as representative as possible, hence providing confidence to the completeness of the PSA study. This study is perhaps one of the first to address classic comprehensive steps in identifying important IEs to be used in a Level-1 PSA study.

  3. Exploring Facilitators and Barriers to Initiation and Completion of the Human Papillomavirus (HPV) Vaccine Series among Parents of Girls in a Safety Net System.

    Science.gov (United States)

    O'Leary, Sean T; Lockhart, Steven; Barnard, Juliana; Furniss, Anna; Dickinson, Miriam; Dempsey, Amanda F; Stokley, Shannon; Federico, Steven; Bronsert, Michael; Kempe, Allison

    2018-01-23

    Objective: To assess, among parents of predominantly minority, low-income adolescent girls who had either not initiated (NI) or not completed (NC) the HPV vaccine series, attitudes and other factors important in promoting the series, and whether attitudes differed by language preference. Design/Methods: From August 2013-October 2013, we conducted a mail survey among parents of girls aged 12-15 years randomly selected from administrative data in a Denver safety net system; 400 parents from each group (NI and NC) were targeted. Surveys were in English or Spanish. The response rate was 37% (244/660; 140 moved or gone elsewhere; 66% English-speaking, 34% Spanish-speaking). Safety attitudes of NIs and NCs differed, with 40% NIs vs. 14% NC's reporting they thought HPV vaccine was unsafe ( p HPV vaccine before, but now I am" (English-speaking, 23%, Spanish-speaking, 50%). Items rated as very important among NIs in the decision regarding vaccination included: more information about safety (74%), more information saying it prevents cancer (70%), and if they knew HPV was spread mainly by sexual contact (61%). Conclusions : Safety concerns, being unaware of the need for multiple doses, and low perceived risk of infection remain significant barriers to HPV vaccination for at-risk adolescents. Some parents' safety concerns do not appear until initial vaccination.

  4. Improving safety in small enterprises through an integrated safety management intervention.

    Science.gov (United States)

    Kines, Pete; Andersen, Dorte; Andersen, Lars Peter; Nielsen, Kent; Pedersen, Louise

    2013-02-01

    This study tests the applicability of a participatory behavior-based injury prevention approach integrated with safety culture initiatives. Sixteen small metal industry enterprises (10-19 employees) are randomly assigned to receive the intervention or not. Safety coaching of owners/managers result in the identification of 48 safety tasks, 85% of which are solved at follow-up. Owner/manager led constructive dialogue meetings with workers result in the prioritization of 29 tasks, 79% of which are accomplished at follow-up. Intervention enterprises have significant increases on six of eight safety-perception-survey factors, while comparisons increase on only one factor. Both intervention and comparison enterprises demonstrate significant increases in their safety observation scores. Interview data validate and supplement these results, providing some evidence for behavior change and the initiation of safety culture change. Given that over 95% of enterprises in most countries have less than 20 employees, there is great potential for adapting this integrated approach to other industries. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

  5. Children's safety initiative: a national assessment of pediatric educational needs among emergency medical services providers.

    Science.gov (United States)

    Hansen, Matthew; Meckler, Garth; Dickinson, Caitlyn; Dickenson, Kathryn; Jui, Jonathan; Lambert, William; Guise, Jeanne-Marie

    2015-01-01

    Emergency medical services (EMS) providers may have critical knowledge gaps in pediatric care due to lack of exposure and training. There is currently little evidence to guide educators to the knowledge gaps that most need to be addressed to improve patient safety. The objective of this study was to identify educational needs of EMS providers related to pediatric care in various domains in order to inform development of curricula. The Children's Safety Initiative-EMS performed a three-phase Delphi survey on patient safety in pediatric emergencies among providers and content experts in pediatric emergency care, including physicians, nurses, and prehospital providers of all levels. Each round included questions related to educational needs of providers or the effect of training on patient safety events. We identified knowledge gaps in the following domains: case exposure, competency and knowledge, assessment and decision making, and critical thinking and proficiency. Individual knowledge gaps were ranked by portion of respondents who ranked them "highly likely" (Likert-type score 7-10 out of 10) to contribute to safety events. There were 737 respondents who were included in analysis of the first phase of the survey. Paramedics were 50.8% of respondents, EMT-basics/first responders were 22%, and physicians 11.4%. The top educational priorities identified in the final round of the survey include pediatric airway management, responder anxiety when working with children, and general pediatric skills among providers. The top three needs in decision-making include knowing when to alter plans mid-course, knowing when to perform an advanced airway, and assessing pain in children. The top 3 technical or procedural skills needs were pediatric advanced airway, neonatal resuscitation, and intravenous/intraosseous access. For neonates, specific educational needs identified included knowing appropriate vital signs and preventing hypothermia. This is the first large-scale Delphi

  6. Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

  7. Interim initial state report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Pers, Karin (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

    2004-07-01

    A thorough description of the initial state of the engineered parts of the repository system is one of the main bases for the SR-Can safety assessment. The initial state refers to the state at the time of deposition for the spent fuel and the engineered barriers and the natural, undisturbed state at the time of beginning of excavation for the repository for the geosphere and the biosphere. The repository system is based on the KBS-3 method, where copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. For the purpose of the safety assessment the engineered portion of the repository system has been divided into a number of consecutive barriers or sub-systems. The importance of a particular feature for safety has influenced the resolution into components. In principle, components close to the source term and those that play an important role for safety are treated in more detail than more peripheral components. For the option with 40 years of reactor operation, the quantity of BWR fuel is estimated at 7200 tonnes and the quantity of PWR fuel at 2300 tonnes. The fuel burn-up may vary from 15 MWd/kgU up to 60 MWd/kg. Geometric aspects of the fuel cladding tubes of importance in the safety assessment are, as a rule, handled sufficiently pessimistically in analyses of radionuclide transport that differences between different fuel types are irrelevant. The relative differences in radionuclide inventory with respect to burn-up are small. Deviations in inventory and deviating or damaged fuel are not considered in the SR-Can interim reporting but will be handled in the final reporting of SR-Can. The canister consists of an inner container, the insert of cast iron and an outer shell of copper. The cast iron insert provides mechanical stability and the copper shell protects against corrosion in the repository environment. The copper shell is 5 cm thick and

  8. Interim initial state report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Pers, Karin

    2004-07-01

    A thorough description of the initial state of the engineered parts of the repository system is one of the main bases for the SR-Can safety assessment. The initial state refers to the state at the time of deposition for the spent fuel and the engineered barriers and the natural, undisturbed state at the time of beginning of excavation for the repository for the geosphere and the biosphere. The repository system is based on the KBS-3 method, where copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. For the purpose of the safety assessment the engineered portion of the repository system has been divided into a number of consecutive barriers or sub-systems. The importance of a particular feature for safety has influenced the resolution into components. In principle, components close to the source term and those that play an important role for safety are treated in more detail than more peripheral components. For the option with 40 years of reactor operation, the quantity of BWR fuel is estimated at 7200 tonnes and the quantity of PWR fuel at 2300 tonnes. The fuel burn-up may vary from 15 MWd/kgU up to 60 MWd/kg. Geometric aspects of the fuel cladding tubes of importance in the safety assessment are, as a rule, handled sufficiently pessimistically in analyses of radionuclide transport that differences between different fuel types are irrelevant. The relative differences in radionuclide inventory with respect to burn-up are small. Deviations in inventory and deviating or damaged fuel are not considered in the SR-Can interim reporting but will be handled in the final reporting of SR-Can. The canister consists of an inner container, the insert of cast iron and an outer shell of copper. The cast iron insert provides mechanical stability and the copper shell protects against corrosion in the repository environment. The copper shell is 5 cm thick and

  9. A study of the state of the art on the determination of the threshold values of the performance indicators for safety systems and initiating events of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, D. I.; Kim, K. Y.; Hwang, M. J.; Park, J. H.; Ha, J. J

    2004-02-01

    The threshold values of Korean Institute of Nuclear Safety (KINS) Performance Indicators (PIs)' determining the safety class of initiating events and safety systems can not sufficiently reflect the operating experience and PSA results of domestic NPPs. Therefore, the state of arts on the PI study of domestic and foreign countries is analyzed in order to reflect the operating experience and PSA results of domestic NPPs in the determination of the threshold values of the PIs for safety systems and initiating events of domestic NPPs. We identified the state of arts of PIs through reviewing the objectives and types of WANO, IAEA, NRC, OECD/NEA and domestic PIs, and the technical issues of the threshold values of SECY 99-007 and NUREG-1753. We also, identified the current status of recently developed MSPI (Mitigating System Performance Index) and IIIEI (Integrated Industry Initiating Event Indicator). From this study of the state of the arts on the PIs, we expect that if the NRC's MSPI and a PI similar to NRC's IIIEI would be introduced into the KINS, it is not necessary to determine the threshold values of PIs applied to the safety systems and initiating events of entire domestic NPPs. Otherwise the threshold values of PIs applied to the individual NPP should be developed using PSA models of typical reactor types. For the active development and use of the risk informed PIs for the domestic NPPs, we expect that the system and component reliability analysis and initiating events analysis for the domestic NPPs, MSPI, IIIEI, and PSA requirements for the PIs be further studied.

  10. Dicty_cDB: VHK810 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available g significant alignments: (bits) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 105 5...e-21 BC138482_1( BC138482 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 103 2e-20 (Q9JLC8) RecName: Full=Sacsi...n; 103 2e-20 BC171956_1( BC171956 |pid:none) Mus musculus sacsin, mRNA (cDNA

  11. Safety performance indicators program

    International Nuclear Information System (INIS)

    Vidal, Patricia G.

    2004-01-01

    In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

  12. Periodic safety review of the HTR-10 safety analysis

    International Nuclear Information System (INIS)

    Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

    2015-01-01

    Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

  13. Upgrading the safety toolkit: Initiatives of the accident analysis subgroup

    International Nuclear Information System (INIS)

    O'Kula, K.R.; Chung, D.Y.

    1999-01-01

    Since its inception, the Accident Analysis Subgroup (AAS) of the Energy Facility Contractors Group (EFCOG) has been a leading organization promoting development and application of appropriate methodologies for safety analysis of US Department of Energy (DOE) installations. The AAS, one of seven chartered by the EFCOG Safety Analysis Working Group, has performed an oversight function and provided direction to several technical groups. These efforts have been instrumental toward formal evaluation of computer models, improving the pedigree on high-use computer models, and development of the user-friendly Accident Analysis Guidebook (AAG). All of these improvements have improved the analytical toolkit for best complying with DOE orders and standards shaping safety analysis reports (SARs) and related documentation. Major support for these objectives has been through DOE/DP-45

  14. AC Initiation System.

    Science.gov (United States)

    An ac initiation system is described which uses three ac transmission signals interlocked for safety by frequency, phase, and power discrimination...The ac initiation system is pre-armed by the application of two ac signals have the proper phases, and activates a load when an ac power signal of the proper frequency and power level is applied. (Author)

  15. In-Office Endoscopic Laryngeal Laser Procedures: A Patient Safety Initiative.

    Science.gov (United States)

    Anderson, Jennifer; Bensoussan, Yael; Townsley, Richard; Kell, Erika

    2018-05-01

    Objective To review complications of in-office endoscopic laryngeal laser procedures after implementation of standardized safety protocol. Methods A retrospective review was conducted of the first 2 years of in-office laser procedures at St Michaels Hospital after the introduction of a standardized safety protocol. The protocol included patient screening, procedure checklist with standardized reporting of processes, medications, and complications. Primary outcomes measured were complication rates of in-office laryngeal laser procedures. Secondary outcomes included hemodynamic changes, local anesthetic dose, laser settings, total laser/procedure time, and incidence of sedation. Results A total of 145 in-office KTP procedures performed on 65 patients were reviewed. In 98% of cases, the safety protocol was fully implemented. The overall complication rate was 4.8%. No major complications were encountered. Minor complications included vasovagal episodes and patient intolerance. The rate of patient intolerance resulting early termination of anticipated procedure was 13.1%. Total local anesthetic dose averaged 172.9 mg lidocaine per procedure. The mean amount of laser energy dispersed was 261.2 J, with mean total procedure time of 48.3 minutes. Sixteen percent of patients had preprocedure sedation. Vital signs were found to vary modestly. Systolic blood pressure was lower postprocedure in 13.8% and symptomatic in 4.1%. Discussion The review of our standardized safety protocol has revealed that in-office laser treatment for laryngeal pathology has extremely low complication rates with safe patient outcomes. Implications for Practice The trend of shifting procedures out of the operating room into the office/clinic setting requires new processes designed to promote patient safety.

  16. Safety analysis SFR 1. Long-term safety

    Energy Technology Data Exchange (ETDEWEB)

    2008-12-15

    An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

  17. Safety analysis SFR 1. Long-term safety

    International Nuclear Information System (INIS)

    2008-12-01

    An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

  18. Safety analysis SFR 1. Long-term safety

    Energy Technology Data Exchange (ETDEWEB)

    2008-12-15

    An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the

  19. Exploring Facilitators and Barriers to Initiation and Completion of the Human Papillomavirus (HPV Vaccine Series among Parents of Girls in a Safety Net System

    Directory of Open Access Journals (Sweden)

    Sean T. O’Leary

    2018-01-01

    Full Text Available Objective: To assess, among parents of predominantly minority, low-income adolescent girls who had either not initiated (NI or not completed (NC the HPV vaccine series, attitudes and other factors important in promoting the series, and whether attitudes differed by language preference. Design/Methods: From August 2013–October 2013, we conducted a mail survey among parents of girls aged 12–15 years randomly selected from administrative data in a Denver safety net system; 400 parents from each group (NI and NC were targeted. Surveys were in English or Spanish. Results: The response rate was 37% (244/660; 140 moved or gone elsewhere; 66% English-speaking, 34% Spanish-speaking. Safety attitudes of NIs and NCs differed, with 40% NIs vs. 14% NC’s reporting they thought HPV vaccine was unsafe (p < 0.0001 and 43% NIs vs. 21% NCs that it may cause long-term health problems (p < 0.001. Among NCs, 42% reported they did not know their daughter needed more shots (English-speaking, 20%, Spanish-speaking 52% and 39% reported that “I wasn’t worried about the safety of the HPV vaccine before, but now I am” (English-speaking, 23%, Spanish-speaking, 50%. Items rated as very important among NIs in the decision regarding vaccination included: more information about safety (74%, more information saying it prevents cancer (70%, and if they knew HPV was spread mainly by sexual contact (61%. Conclusions: Safety concerns, being unaware of the need for multiple doses, and low perceived risk of infection remain significant barriers to HPV vaccination for at-risk adolescents. Some parents’ safety concerns do not appear until initial vaccination.

  20. Safety Research Opportunities Post-Fukushima. Initial Report of the Senior Expert Group

    International Nuclear Information System (INIS)

    Baek, Won-Pil; Yang, Joon-Eon; Ball, Joanne; Glowa, Glenn; Bisconti, Giulia; Peko, Damian; Bolshov, Leonid; Burgazzi, Luciano; De Rosa, Felice; Conde, Jose M.; Cook, Gary; Evrard, Jean-Michel; Jacquemain, Didier; Funaki, Kentaro; Uematsu, Mari Marianne; Miyoshi, Katsumasa; Tatematsu, Atsushi; Hirano, Masashi; Hoshi, Harutaka; Kawaragi, Chie; Kobayashi, Youko; Sakamoto, Kazunobu; Journeau, Christophe; Kim, Han-Chul; Klein-Hessling, Walter; Sonnenkalb, Martin; Koganeya, Toshiyuki; White, Andrew; ); Lind, Terttaliisa; Zimmermann, Martin; Lindholm, Ilona; Castelo Lopez, Carlos; Nagase, Fumihisa; Washiya, Tadahiro; Oima, Hirofumi; Okada, Hiro; Richards, Stuart; West, Steven; Sandberg, Nils; Suzuki, Shunichi; Vitanza, Carlo; Yamanaka, Yasunori

    2017-02-01

    One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are identified and that research programs to address these gaps are being instituted. In recognition of broad international interest in additional information that could be gained from post-accident examinations related to Fukushima Daiichi, Japan recommended to the Committee on the Safety of Nuclear Installations (CSNI) in June 2013 that a process be developed to identify and follow up on opportunities to address safety research gaps. Consequently, a Senior Expert Group (SEG) on Safety Research Opportunities post-Fukushima (SAREF) was formed. The members of the group are senior technical experts from technical support organisations, nuclear regulatory authorities and Japanese organisations responsible for planning and execution of Fukushima Daiichi decommissioning. The domain of interest for the group is activities that address safety research knowledge gaps and also the needs of Fukushima Daiichi decommissioning. SEG on SAREF identified areas where these two interests intersect or overlap, and activities that could be undertaken to generate information of common benefit. The group's output is documented in this report; Chapter 2 describes the current status of the damaged units at Fukushima Daiichi NPS; Chapter 3 summarises safety research areas of common interest; Chapter 4 summarises the safety research activities recommended as short-term projects; Chapter 5 summarises those as long-term considerations; Chapter 6 supplies conclusions and recommendations. The appendix contains detailed information compiled by the SEG members on all safety research areas of interest

  1. Nuclear Safety Charter

    International Nuclear Information System (INIS)

    2008-01-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and subcontractors are treated

  2. Calculation and definition of safety indicators

    International Nuclear Information System (INIS)

    Cristian, I.; Branzeu, N.; Vidican, D.; Vladescu, G.

    1997-01-01

    This paper presents, based on Cernavoda safety indicators proposal, the purpose definition and calculation formulas for each of the selected safety indicators. Five categories of safety indicators for Cernavoda Unit 1 were identified, namely: overall plant safety performance; initiating events; safety system availability, physical barrier integrity; indirect indicators. Definition, calculation and use of some safety indicators are shown in a tabular form. (authors)

  3. Safety Training: places available in October 2014

    CERN Multimedia

    2014-01-01

    There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue. Safety Training, HSE Unit safety-training@cern.ch Title of the course EN Title of the course FR Date Hours Language Chemical Safety ATEX Habilitation - Level 2 Habilitation ATEX - Niveau 2 16-Oct-14 to 17-Oct-14 9:00 - 17:30 French Cryogenic Safety Cryogenic Safety - Fundamentals Sécurité Cryogénie - Fondamentaux 23-Oct-14 10:00 - 12:00 English Cryogenic Safety - Helium Transfer Sécurité Cryogénie - Transfert d'hélium 30-Oct-14 9:30 - 12:00 English Electrical Safety Habilitation Electrique - Electrician Low Voltage - Initial Habilitation électrique - Électricien basse tension - Initial 02-Oct-14 to 06-Oct-14 9:00 - 17:30 English 20-Oct-14 to 22-Oct-14 9:00 -...

  4. Safety design

    International Nuclear Information System (INIS)

    Kunitomi, Kazuhiko; Shiozawa, Shusaku

    2004-01-01

    JAERI established the safety design philosophy of the HTTR based on that of current reactors such as LWR in Japan, considering inherent safety features of the HTTR. The strategy of defense in depth was implemented so that the safety engineering functions such as control of reactivity, removal of residual heat and confinement of fission products shall be well performed to ensure safety. However, unlike the LWR, the inherent design features of the high-temperature gas-cooled reactor (HTGR) enables the HTTR meet stringent regulatory criteria without much dependence on active safety systems. On the other hand, the safety in an accident typical to the HTGR such as the depressurization accident initiated by a primary pipe rupture shall be ensured. The safety design philosophy of the HTTR considers these unique features appropriately and is expected to be the basis for future Japanese HTGRs. This paper describes the safety design philosophy and safety evaluation procedure of the HTTR especially focusing on unique considerations to the HTTR. Also, experiences obtained from an HTTR safety review and R and D needs for establishing the safety philosophy for the future HTGRs are reported

  5. Sustainable Development of Food Safety

    DEFF Research Database (Denmark)

    Fabech, B.; Georgsson, F.; Gry, Jørn

    to food safety - Strengthen efforts against zoonoses and pathogenic microorganisms - Strengthen safe food handling and food production in industry and with consumers - Restrict the occurrence of chemical contaminants and ensure that only well-examined production aids, food additives and flavours are used...... - Strengthen scientific knowledge of food safety - Strengthen consumer knowledge The goals for sustainable development of food safety are listed from farm to fork". All of the steps and areas are important for food safety and consumer protection. Initiatives are needed in all areas. Many of the goals...... in other areas. It should be emphasized that an indicator will be an excellent tool to assess the efficacy of initiatives started to achieve a goal. Conclusions from the project are: - Sustainable development in food safety is important for humanity - Focus on the crucial goals would optimize the efforts...

  6. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    The objective of this Safety Guide is to provide harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. It provides information on the utilization of the results of such analysis for safety and reliability improvements. The Safety Guide addresses conservative, best estimate and uncertainty evaluation approaches to deterministic safety analysis and is applicable to current and future designs. Contents: 1. Introduction; 2. Grouping of initiating events and associated transients relating to plant states; 3. Deterministic safety analysis and acceptance criteria; 4. Conservative deterministic safety analysis; 5. Best estimate plus uncertainty analysis; 6. Verification and validation of computer codes; 7. Relation of deterministic safety analysis to engineering aspects of safety and probabilistic safety analysis; 8. Application of deterministic safety analysis; 9. Source term evaluation for operational states and accident conditions; References

  7. Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

    Science.gov (United States)

    Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

    2013-12-01

    This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

  8. Dicty_cDB: VHC102 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available ucing significant alignments: (bits) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 1...05 4e-21 BC138482_1( BC138482 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 103 2e-20 (Q9JLC8) RecName: Full=Sacsi...n; 103 2e-20 BC171956_1( BC171956 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 103 2e-20 CP0015

  9. Safety analysis for research reactors

    International Nuclear Information System (INIS)

    2008-01-01

    The aim of safety analysis for research reactors is to establish and confirm the design basis for items important to safety using appropriate analytical tools. The design, manufacture, construction and commissioning should be integrated with the safety analysis to ensure that the design intent has been incorporated into the as-built reactor. Safety analysis assesses the performance of the reactor against a broad range of operating conditions, postulated initiating events and other circumstances, in order to obtain a complete understanding of how the reactor is expected to perform in these situations. Safety analysis demonstrates that the reactor can be kept within the safety operating regimes established by the designer and approved by the regulatory body. This analysis can also be used as appropriate in the development of operating procedures, periodic testing and inspection programmes, proposals for modifications and experiments and emergency planning. The IAEA Safety Requirements publication on the Safety of Research Reactors states that the scope of safety analysis is required to include analysis of event sequences and evaluation of the consequences of the postulated initiating events and comparison of the results of the analysis with radiological acceptance criteria and design limits. This Safety Report elaborates on the requirements established in IAEA Safety Standards Series No. NS-R-4 on the Safety of Research Reactors, and the guidance given in IAEA Safety Series No. 35-G1, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, providing detailed discussion and examples of related topics. Guidance is given in this report for carrying out safety analyses of research reactors, based on current international good practices. The report covers all the various steps required for a safety analysis; that is, selection of initiating events and acceptance criteria, rules and conventions, types of safety analysis, selection of

  10. Probability safety assessment of the Kozloduy-5 and Kozloduy-6 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Boyadzhiev, A; Manchev, B [Risk Engineering Ltd., Sofia (Bulgaria)

    1996-12-31

    A probability safety assessment (PSA) of Level 1 (assessment of plant failures leading to the determination of core damage frequency) has been carried out for the NPP Kozloduy Units 5 and 6 (reactors WWER-1000). The scope of the study includes all significant accident initiators including seismic (earthquake) and fire initiators. Event trees for all initiators and fault trees for front line systems, support systems and major safety systems have been built. A distribution of the different initiators has been established as follows: internal initiators - 85%, seismic initiators - 5%, fire initiators- 10%. The loss of offsite power was identified as main contributor from the internal initiators with frequency 1,1.10{sup -4}/y. It is concluded that the safety functions of WWER-1000 are adequately covered by the safety systems. 4 refs., 2 tabs.

  11. Selection of initial events of accelerator driven subcritical system

    International Nuclear Information System (INIS)

    Wang Qianglong; Hu Liqin; Wang Jiaqun; Li Yazhou; Yang Zhiyi

    2013-01-01

    The Probabilistic Safety Assessment (PSA) is an important tool in reactor safety analysis and a significant reference to the design and operation of reactor. It is the origin and foundation of the PSA for a reactor to select the initial events. Accelerator Driven Subcritical System (ADS) has advanced design characteristics, complicated subsystems and little engineering and operating experience, which makes it much more difficult to identify the initial events of ADS. Based on the current design project of ADS, the system's safety characteristics and special issues were analyzed in this article. After a series of deductions with Master Logic Diagram (MLD) and considering the relating experience of other advanced research reactors, a preliminary initial events was listed finally, which provided the foundation for the next safety assessment. (authors)

  12. Intensive care unit nurses' perceptions of safety after a highly specific safety intervention.

    Science.gov (United States)

    Elder, N C; Brungs, S M; Nagy, M; Kudel, I; Render, M L

    2008-02-01

    It is unknown if successful changes in specific safety practices in the intensive care unit (ICU) generalize to broader concepts of patient safety by staff nurses. To explore perceptions of patient safety among nursing staff in ICUs following participation in a safety project that decreased hospital acquired infections. After implementation of practices that reduced catheter-related bloodstream infections in ICUs at four community hospitals, ICU nurses participated in focus groups to discuss patient safety. Audiotapes from the focus groups were transcribed, and two independent reviewers categorised the data which were triangulated with responses from selected questions of safety climate surveys and with the safety checklists used by management leadership on walk rounds. Thirty-three nurses attended eight focus groups; 92 nurses and managers completed safety climate surveys, and three separate leadership checklists were reviewed. In focus groups, nurses predominantly related patient safety to dangers in the physical environment (eg, bed rails, alarms, restraints, equipment, etc.) and to medication administration. These areas also represented 47% of checklist items from leadership walk rounds. Nurses most frequently mentioned self-initiated "double checking" as their main safety task. Focus-group participants and survey responses both noted inconsistency between management's verbal and written commitment compared with their day-to-day support of patient safety issues. ICU nurses who participated in a project to decrease hospital acquired infections did not generalize their experience to other aspects of patient safety or relate it to management's interest in patient safety. These findings are consistent with many adult learning theories, where self-initiated tasks, combined with immediate, but temporary problem-solving, are stronger learning forces than management-led activities with delayed feedback.

  13. A Response to Proposed Equal Employment Opportunity Commission Regulations on Employer-Sponsored Health, Safety, and Well-Being Initiatives.

    Science.gov (United States)

    2016-03-01

    The aim of this study was to identify areas of consensus in response to proposed Equal Employment Opportunity Commission Americans with Disabilities Act of 1990 and Genetic Information Nondiscrimination Act of 2008 regulations on employer-sponsored health, safety, and well-being initiatives. The consensus process included review of existing and proposed regulations, identification of key areas where consensus is needed, and a methodical consensus-building process. Stakeholders representing employees, employers, consulting organizations, and wellness providers reached consensus around five areas, including adequate privacy notice on how medical data are collected, used, and protected; effective, equitable use of inducements that influence participation in programs; observance of reasonable alternative standards; what constitutes reasonably designed programs; and the need for greater congruence between federal agency regulations. Employee health and well-being initiatives that are in accord with federal regulations are comprehensive, evidence-based, and are construed as voluntary by employees and regulators alike.

  14. Farmworkers at the border: a bilingual initiative for occupational health and safety.

    Science.gov (United States)

    Acosta, Martha Soledad Vela; Sechrest, Lee; Chen, Mei-Kuang

    2009-01-01

    Bilingual and bicultural occupational health and safety interventions for Hispanic farmworkers are extremely rare and, because of language barriers and cultural differences, issues important to their health and safety on the job remain unaddressed. We designed, conducted, and assessed the first bilingual occupational health and safety education program for farmworkers attending High School Equivalency Programs (HEPs). We took an interdisciplinary participatory approach by integrating educators and researchers with a community advisory board to guide development, evaluation, and implementation of Work Safely-Trabaje con Cuidado Curriculum (Curriculum), a bilingual occupational health and safety curriculum. We created a quasi-experimental design using mixed-method evaluation (quantitative and qualitative elements) via pre- and posttest comparisons, follow-up surveys, and focus groups assessing the Curriculum effect on knowledge, safety risk perception (SRP), and safety behavior. Focus groups and follow-up surveys reflected success and acceptance of the Curriculum among participating farmworkers under the study's logic model. Completion of the Curriculum resulted in statistically significant improvements in the combined score of knowledge and SRP at the posttest (p = 0.001) and follow-up survey (p = 0.02) in the intervention group. After completing this study, the Curriculum was permanently adopted by the two high school equivalency sites involved. The participatory approach resulted in integration of community and applied research partnership. The potential to expand use of this Curriculum by other HEP sites can further assess effectiveness and external validity among underserved minority groups.

  15. Initial perspectives on process threat management

    International Nuclear Information System (INIS)

    Whiteley, James R. Rob; Mannan, M. Sam

    2004-01-01

    Terrorist and criminal acts are now considered credible risks in the process industries. Deliberate attacks on the nation's petroleum refineries and chemical plants would pose a significant threat to public welfare, national security, and the US economy. To-date, the primary response of government and industry has been on improved security to prevent attacks and the associated consequences. While prevention is clearly preferred, the potential for successful attacks must be addressed. If plant security is breached, the extent of the inflicted damage is determined by the available plant safety systems and procedures. We refer to this 'inside the gate' response as process threat management. The authors have initiated a joint industry/academia study to address: - the level of safety provided by existing plant equipment and safety systems in response to a terrorist act, and; - identification of process (rather than security) needs or opportunities to address this new safety concern. This paper describes the initial perspectives and issues identified by the team at the beginning of the study

  16. Patient safety culture in primary care

    NARCIS (Netherlands)

    Verbakel, N.J.

    2015-01-01

    Background A constructive patient safety culture is a main prerequisite for patient safety and improvement initiatives. Until now, patient safety culture (PSC) research was mainly focused on hospital care, however, it is of equal importance in primary care. Measuring PSC informs practices on their

  17. Fire safety of wood construction

    Science.gov (United States)

    Robert H. White; Mark A. Dietenberger

    2010-01-01

    Fire safety is an important concern in all types of construction. The high level of national concern for fire safety is reflected in limitations and design requirements in building codes. These code requirements and related fire performance data are discussed in the context of fire safety design and evaluation in the initial section of this chapter. Because basic data...

  18. Safety of a DVT chemoprophylaxis protocol following traumatic brain injury: a single center quality improvement initiative.

    Science.gov (United States)

    Nickele, Christopher M; Kamps, Timothy K; Medow, Joshua E

    2013-04-01

    Venous thromboembolism (VTE) is a complication that affects approximately 30 % of moderate and severe traumatic brain injury (TBI) patients when pharmacologic prophylaxis is not used. Following TBI, specifically in the case of contusions, the safety and efficacy of pharmacologic thromboembolism prophylaxis (PTP) has been studied only in small sample sizes. In this study, we attempt to assess the safety and efficacy of a PTP protocol for TBI patients, as a quality improvement (QI) initiative, in the neuroscience intensive care unit (NSICU). Between January 1st and December 31st, 2009, consecutive patients discharged from the University of Wisconsin NSICU after >a 48 h minimum stay were evaluated as part of a QI project. A protocol for the initiation of PTP was designed and implemented for NSICU patients. The protocol did not vary based on type of intracranial injury. The rate of VTE was reported as was heparin-induced thrombocytopenia and PTP-related expansion of intracranial hemorrhage (IH) requiring reoperation. The number of patients receiving PTP and the timing of therapy were tracked. Patients were excluded for persistent coagulopathy, other organ system bleeding (such as the gastrointestinal tract), or pregnancy. Faculty could opt out of the protocol without reason. Using the same criteria, patients discharged during the preceding 6 months, from July 1st to December 31st, 2008, were evaluated as controls as the PTP protocol was not in effect during this time. During the control period, there were 48 head trauma admissions who met the inclusion criteria. In 22 patients (45.8 %), PTP was initiated at an average of 4.9 ± 5.4 days after admission. During the protocol period, there were 87 head trauma admissions taken from 1,143 total NSICU stays who met criteria. In 63 patients (72.4 %), the care team in the NSICU successfully initiated PTP, at an average of 3.4 ± 2.8 days after admission. All 87 trauma patients were analyzed, and the rate of clinically

  19. COMPRESS - a computerized reactor safety system

    International Nuclear Information System (INIS)

    Vegh, E.

    1986-01-01

    The computerized reactor safety system, called COMPRESS, provides the following services: scram initiation; safety interlockings; event recording. The paper describes the architecture of the system and deals with reliability problems. A self-testing unit checks permanently the correct operation of the independent decision units. Moreover the decision units are tested by short pulses whether they can initiate a scram. The self-testing is described in detail

  20. Development and Psychometric Analysis of a Nurses' Attitudes and Skills Safety Scale: Initial Results.

    Science.gov (United States)

    Armstrong, Gail E; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

    Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses' perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses' perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses' perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices.

  1. The analysis of the initiating events in thorium-based molten salt reactor

    International Nuclear Information System (INIS)

    Zuo Jiaxu; Song Wei; Jing Jianping; Zhang Chunming

    2014-01-01

    The initiation events analysis and evaluation were the beginning of nuclear safety analysis and probabilistic safety analysis, and it was the key points of the nuclear safety analysis. Currently, the initiation events analysis method and experiences both focused on water reactor, but no methods and theories for thorium-based molten salt reactor (TMSR). With TMSR's research and development in China, the initiation events analysis and evaluation was increasingly important. The research could be developed from the PWR analysis theories and methods. Based on the TMSR's design, the theories and methods of its initiation events analysis could be researched and developed. The initiation events lists and analysis methods of the two or three generation PWR, high-temperature gascooled reactor and sodium-cooled fast reactor were summarized. Based on the TMSR's design, its initiation events would be discussed and developed by the logical analysis. The analysis of TMSR's initiation events was preliminary studied and described. The research was important to clarify the events analysis rules, and useful to TMSR's designs and nuclear safety analysis. (authors)

  2. Development and Psychometric Analysis of a Nurses’ Attitudes and Skills Safety Scale: Initial Results

    Science.gov (United States)

    Armstrong, Gail E.; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

    2016-01-01

    Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses’ perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses’ perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses’ perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices. PMID:27479518

  3. Impact of Pre-Initiators on PSA in Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ochirbat, Chimedtseren [KAIST, Daejeon (Korea, Republic of); Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    Most of nuclear power plants had already conducted PSA work to examine their plant safety for identifying vulnerability and preparing the mitigating strategies for severe accident. However, the PSA for research reactor has been conducted limitedly comparing with nuclear power plants due to lack of awareness and resources. Most of PSA results demonstrated that human failure events (HFEs) take a major role of risk contributor in terms of core damage frequency. HFEs are categorized as the following three types: pre-initiating event interaction (e.g., maintenance of errors, testing errors, calibration errors), initiating event related interactions (e.g., human error causing loss of power, human error causing system trip), and post-initiating event (e.g., all action actuating manual safety system backup of an automatic system). Lack of resources and utilization of research reactor calls a vicious circle in terms of safety degradation. The safety degradation poses the vulnerability of human failure during research reactor utilization process. Typically, evaluation of pre-initiators related to test and maintenance are not taking into account in PSA for research reactors. This paper aims to investigate the impact of pre-initiating events related to test and maintenance activities on PSA results in terms of core damage frequency for a research reactor.

  4. Impact of Pre-Initiators on PSA in Research Reactor

    International Nuclear Information System (INIS)

    Ochirbat, Chimedtseren; Kim, Sok Chul

    2014-01-01

    Most of nuclear power plants had already conducted PSA work to examine their plant safety for identifying vulnerability and preparing the mitigating strategies for severe accident. However, the PSA for research reactor has been conducted limitedly comparing with nuclear power plants due to lack of awareness and resources. Most of PSA results demonstrated that human failure events (HFEs) take a major role of risk contributor in terms of core damage frequency. HFEs are categorized as the following three types: pre-initiating event interaction (e.g., maintenance of errors, testing errors, calibration errors), initiating event related interactions (e.g., human error causing loss of power, human error causing system trip), and post-initiating event (e.g., all action actuating manual safety system backup of an automatic system). Lack of resources and utilization of research reactor calls a vicious circle in terms of safety degradation. The safety degradation poses the vulnerability of human failure during research reactor utilization process. Typically, evaluation of pre-initiators related to test and maintenance are not taking into account in PSA for research reactors. This paper aims to investigate the impact of pre-initiating events related to test and maintenance activities on PSA results in terms of core damage frequency for a research reactor

  5. PWR reload safety evaluation methodology

    International Nuclear Information System (INIS)

    Doshi, P.K.; Chapin, D.L.; Love, D.S.

    1993-01-01

    The current practice for WWER safety analysis is to prepare the plant Safety Analysis Report (SAR) for initial plant operation. However, the existing safety analysis is typically not evaluated for reload cycles to confirm that all safety limits are met. In addition, there is no systematic reanalysis or reevaluation of the safety analyses after there have been changes made to the plant. The Westinghouse process is discussed which is in contrast to this and in which the SAR conclusions are re-validated through evaluation and/or analysis of each reload cycle. (Z.S.)

  6. Institutional Response to Ohio's Campus Safety Initiatives: A Post-Virginia Tech Analysis

    Science.gov (United States)

    Jackson, Natalie Jo

    2009-01-01

    The purpose of this study was to examine how institutions of higher education were responding to unprecedented state involvement in campus safety planning and policymaking in the aftermath of the Virginia Tech tragedy. Focused on Ohio, a state in which a state-level task force was convened and charged to promulgate campus safety recommendations…

  7. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  8. A total safety management model

    International Nuclear Information System (INIS)

    Obadia, I.J.; Vidal, M.C.R.; Melo, P.F.F.F.

    2002-01-01

    In nuclear organizations, quality and safety are inextricably linked. Therefore, the search for excellence means reaching excellence in nuclear safety. The International Atomic Energy Agency, IAEA, developed, after the Chernobyl accident, the organizational approach for improving nuclear safety based on the safety culture, which requires a framework necessary to provide modifications in personnel attitudes and behaviors in situations related to safety. This work presents a Total Safety Management Model, based on the Model of Excellence of the Brazilian Quality Award and on the safety culture approach, which represents an alternative to this framework. The Model is currently under validation at the Nuclear Engineering Institute, in Rio de Janeiro, Brazil, and the results of its initial safety culture self assessment are also presented and discussed. (author)

  9. Dicty_cDB: VHK791 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available ificant alignments: (bits) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL15...142916_1( BC142916 |pid:none) Danio rerio hypothetical LOC555303... 105 5e-21 BC171956_1( BC171956 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 103 1e-20 BC138482_1( BC138482 |pid:none) Mus musculus sacsin, mRNA ...(cDNA cl... 103 1e-20 (Q9JLC8) RecName: Full=Sacsin; 103 1e-20 AB006708_10( AB006

  10. SP-100 initial startup and restart control strategy

    International Nuclear Information System (INIS)

    Halfen, F.J.; Wong, K.K.; Switick, D.M.; Shukla, J.N.

    1992-01-01

    This paper reports that recent Generic Flight System (GFS) updates have necessitated revisions in the initial startup and restart control strategies. The design changes that have had the most impact on the control strategies are the addition of the Auxiliary Cooling and Thaw (ACT) system for preheating the lithium filled components, changes in the reactivity worths of the reflectors and safety-rods such that initial cold criticality is achieved with only a small amount of reflector movement following the withdrawal of the safety-rods, and the removal of the scram function from the reflectors. Revised control and operating strategies have been developed and tested using the SP-100 dynamic simulation model, ARIES-GFS. The change in the total reactivity worths of the reflectors and safety-rods has eliminated the need for the use of fast and slow reflector drive speeds during the initial on-orbit approach to criticality. The relatively fast removal of the safety-rods results in a near-critical condition so that the use of slow moving (single speed) reflector drives does not add significant time to achieve full power for the initial startup. The use of the ACT system (with its NaK trace-lines for preheating and auxiliary cooling) affects the main Thermoelectric Electro-Magnetic (TEM) pump startup and the time after a shutdown before freezing occurs in the main heat transfer systems

  11. Counterheroism, common knowledge, and ergonomics: concepts from aviation that could improve patient safety.

    Science.gov (United States)

    Lewis, Geraint H; Vaithianathan, Rhema; Hockey, Peter M; Hirst, Guy; Bagian, James P

    2011-03-01

    Many safety initiatives have been transferred successfully from commercial aviation to health care. This article develops a typology of aviation safety initiatives, applies this to health care, and proposes safety measures that might be adopted more widely. It then presents an economic framework for determining the likely costs and benefits of different patient safety initiatives. This article describes fifteen examples of error countermeasures that are used in public transport aviation, many of which are not routinely used in health care at present. Examples are the sterile cockpit rule, flight envelope protection, the first-names-only rule, and incentivized no-fault reporting. It develops a conceptual schema that is then used to argue why analogous initiatives might be usefully applied to health care and why physicians may resist them. Each example is measured against a set of economic criteria adopted from the taxation literature. The initiatives considered in the article fall into three themes: safety concepts that seek to downplay the role of heroic individuals and instead emphasize the importance of teams and whole organizations; concepts that seek to increase and apply group knowledge of safety information and values; and concepts that promote safety by design. The salient costs to be considered by organizations wishing to adopt these suggestions are the compliance costs to clinicians, the administration costs to the organization, and the costs of behavioral distortions. This article concludes that there is a range of safety initiatives used in commercial aviation that could have a positive impact on patient safety, and that adopting such initiatives may alter the safety culture of health care teams. The desirability of implementing each initiative, however, depends on the projected costs and benefits, which must be assessed for each situation. © 2011 Milbank Memorial Fund. Published by Wiley Periodicals Inc.

  12. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    Energy Technology Data Exchange (ETDEWEB)

    E.N. Lindner

    2004-12-03

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly

  13. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    International Nuclear Information System (INIS)

    E.N. Lindner

    2004-01-01

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly

  14. The Department of Energy nuclear criticality safety program

    International Nuclear Information System (INIS)

    Felty, J.R.

    2004-01-01

    This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

  15. Safety culture activities in HANARO

    International Nuclear Information System (INIS)

    Lim, I. C.; Park, C.; Hwang, S. R.; Choi, H. Y.; Jeon, B. J.

    2002-01-01

    The yearly operation time and the number of users in HANARO are increasing since its initial criticality has been achieved in 1995. This achievement is partly in debt to the spread of safety culture to operators and reactor users. In this paper, the activities done by the reactor operation organization on safety culture are described, and their further efforts identified to be necessary for the improvement and dissemination of safety culture and are presented

  16. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  17. Leadership for safety: industrial experience.

    Science.gov (United States)

    Flin, R; Yule, S

    2004-12-01

    The importance of leadership for effective safety management has been the focus of research attention in industry for a number of years, especially in energy and manufacturing sectors. In contrast, very little research into leadership and safety has been carried out in medical settings. A selective review of the industrial safety literature for leadership research with possible application in health care was undertaken. Emerging findings show the importance of participative, transformational styles for safety performance at all levels of management. Transactional styles with attention to monitoring and reinforcement of workers' safety behaviours have been shown to be effective at the supervisory level. Middle managers need to be involved in safety and foster open communication, while ensuring compliance with safety systems. They should allow supervisors a degree of autonomy for safety initiatives. Senior managers have a prime influence on the organisation's safety culture. They need to continuously demonstrate a visible commitment to safety, best indicated by the time they devote to safety matters.

  18. Implementing the Comprehensive Unit-Based Safety Program (CUSP) to Improve Patient Safety in an Academic Primary Care Practice.

    Science.gov (United States)

    Pitts, Samantha I; Maruthur, Nisa M; Luu, Ngoc-Phuong; Curreri, Kimberly; Grimes, Renee; Nigrin, Candace; Sateia, Heather F; Sawyer, Melinda D; Pronovost, Peter J; Clark, Jeanne M; Peairs, Kimberly S

    2017-11-01

    While there is growing awareness of the risk of harm in ambulatory health care, most patient safety efforts have focused on the inpatient setting. The Comprehensive Unit-based Safety Program (CUSP) has been an integral part of highly successful safety efforts in inpatient settings. In 2014 CUSP was implemented in an academic primary care practice. As part of CUSP implementation, staff and clinicians underwent training on the science of safety and completed a two-question safety assessment survey to identify safety concerns in the practice. The concerns identified by team members were used to select two initial safety priorities. The impact of CUSP on safety climate and teamwork was assessed through a pre-post comparison of results on the validated Safety Attitudes Questionnaire. Ninety-six percent of staff completed science of safety training as part of CUSP implementation, and 100% of staff completed the two-question safety assessment. The most frequently identified safety concerns were related to medications (n = 11, 28.2), diagnostic testing (n = 9, 25), and communication (n = 5, 14). The CUSP team initially prioritized communication and infection control, which led to standardization of work flows within the practice. Six months following CUSP implementation, large but nonstatistically significant increases were found for the percentage of survey respondents who reported knowledge of the proper channels for questions about patient safety, felt encouraged to report safety concerns, and believed that the work setting made it easy to learn from the errors of others. CUSP is a promising tool to improve safety climate and to identify and address safety concerns within ambulatory health care. Copyright © 2017 The Joint Commission. Published by Elsevier Inc. All rights reserved.

  19. A Study of Time Response for Safety-Related Operator Actions in Non-LOCA Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Min Seok; Lee, Sang Seob; Park, Min Soo; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO E and C Company, Daejeon (Korea, Republic of)

    2014-10-15

    The classification of initiating events for safety analysis report (SAR) chapter 15 is categorized into moderate frequency events (MF), infrequent events (IF), and limiting faults (LF) depending on the frequency of its occurrence. For the non-LOCA safety analysis with the purpose to get construction or operation license, however, it is assumed that the operator response action to mitigate the events starts at 30 minutes after the initiation of the transient regardless of the event categorization. Such an assumption of corresponding operator response time may have over conservatism with the MF and IF events and results in a decrease in the safety margin compared to its acceptance criteria. In this paper, the plant conditions (PC) are categorized with the definitions in SAR 15 and ANS 51.1. Then, the consequence of response for safety-related operator action time is determined based on the PC in ANSI 58.8. The operator response time for safety analysis regarding PC are reviewed and suggested. The clarifying alarm response procedure would be required for the guideline to reduce the operator response time when the alarms indicate the occurrence of the transient.

  20. U.S. Coast Guard, Office of Boating Safety

    Science.gov (United States)

    ... Initiatives Carbon Monoxide Life Jacket Wear / Wearing your Life Jacket Float Planning Regulations State Boating Laws Navigation Rules Recalls & Safety Defects Manufacturers Identification Consumer Safety Defect ...

  1. Criticality Safety in the Handling of Fissile Material. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-05-15

    This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The guidance and recommendations are applicable to both regulatory bodies and operating organizations. The objectives of criticality safety are to prevent a self-sustained nuclear chain reaction and to minimize the consequences of this if it were to occur. The Safety Guide makes recommendations on how to ensure subcriticality in systems involving fissile materials during normal operation, anticipated operational occurrences, and, in the case of accident conditions, within design basis accidents, from initial design through commissioning, operation, and decommissioning and disposal.

  2. Probabilistic safety assessment goals in Canada

    International Nuclear Information System (INIS)

    Snell, V.G.

    1986-01-01

    CANDU safety philosphy, both in design and in licensing, has always had a strong bias towards quantitative probabilistically-based goals derived from comparative safety. Formal probabilistic safety assessment began in Canada as a design tool. The influence of this carried over later on into the definition of the deterministic safety guidelines used in CANDU licensing. Design goals were further developed which extended the consequence/frequency spectrum of 'acceptable' events, from the two points defined by the deterministic single/dual failure analysis, to a line passing through lower and higher frequencies. Since these were design tools, a complete risk summation was not necessary, allowing a cutoff at low event frequencies while preserving the identification of the most significant safety-related events. These goals gave a logical framework for making decisions on implementing design changes proposed as a result of the Probabilistic Safety Analysis. Performing this analysis became a regulatory requirement, and the design goals remained the framework under which this was submitted. Recently, there have been initiatives to incorporate more detailed probabilistic safety goals into the regulatory process in Canada. These range from far-reaching safety optimization across society, to initiatives aimed at the nuclear industry only. The effectiveness of the latter is minor at very low and very high event frequencies; at medium frequencies, a justification against expenditures per life saved in other industries should be part of the goal setting

  3. Complementary safety assessments - Report by the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    2011-12-01

    As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

  4. Safety culture development in nuclear electric plc

    International Nuclear Information System (INIS)

    Gibson, G.P.; Low, M.B.J.

    1995-01-01

    Nuclear Electric plc (NE) has always given the highest priority to safety. However, past emphasis has been directed towards ensuring safety thorough engineering design and hazard control procedures. Whilst the company did achieve high safety standards, particularly with respect to accidents, it was recognized that further improvements could be obtained. Analysis of the safety performance across a wide range of industries showed that the key to improving safety performance lay in developing a strong safety culture within the company. Over the last five years, NE has made great strides to improve its safety culture. This has resulted in a considerable improvement in its measured safety performance indicators, such as the number of incidents at international nuclear event scale (INES) rating 1, the number of lost time accidents and the collective radiation dose. However, despite this success, the company is committed to further improvement and a means by which this process becomes self-sustaining. In this way the company will achieve its prime goal, to ''ensure the safety of people, plant and the environment''. The paper provides an overview of the development of safety culture in NE since its formation in November 1989. It describes the research and international developments that have influenced the company's understanding of safety culture, the key initiatives that the company has undertaken to enhance its safety culture and the future initiatives being considered to ensure continual improvement. (author). 5 refs, 2 figs, 2 tabs

  5. Efficacy and Safety of Three Antiretroviral Regimens for Initial Treatment of HIV-1: A Randomized Clinical Trial in Diverse Multinational Settings

    Science.gov (United States)

    Campbell, Thomas B.; Smeaton, Laura M.; Kumarasamy, N.; Flanigan, Timothy; Klingman, Karin L.; Firnhaber, Cynthia; Grinsztejn, Beatriz; Hosseinipour, Mina C.; Kumwenda, Johnstone; Lalloo, Umesh; Riviere, Cynthia; Sanchez, Jorge; Melo, Marineide; Supparatpinyo, Khuanchai; Tripathy, Srikanth; Martinez, Ana I.; Nair, Apsara; Walawander, Ann; Moran, Laura; Chen, Yun; Snowden, Wendy; Rooney, James F.; Uy, Jonathan; Schooley, Robert T.; De Gruttola, Victor; Hakim, James Gita; Swann, Edith; Barnett, Ronald L.; Brizz, Barbara; Delph, Yvette; Gettinger, Nikki; Mitsuyasu, Ronald T.; Eshleman, Susan; Safren, Steven; Fiscus, Susan A.; Andrade, Adriana; Haas, David W.; Amod, Farida; Berthaud, Vladimir; Bollinger, Robert C.; Bryson, Yvonne; Celentano, David; Chilongozi, David; Cohen, Myron; Collier, Ann C.; Currier, Judith Silverstein; Cu-Uvin, Susan; Eron, Joseph; Flexner, Charles; Gallant, Joel E.; Gulick, Roy M.; Hammer, Scott M.; Hoffman, Irving; Kazembe, Peter; Kumwenda, Newton; Lama, Javier R.; Lawrence, Jody; Maponga, Chiedza; Martinson, Francis; Mayer, Kenneth; Nielsen, Karin; Pendame, Richard B.; Ramratnam, Bharat; Sanne, Ian; Severe, Patrice; Sirisanthana, Thira; Solomon, Suniti; Tabet, Steve; Taha, Taha; van der Horst, Charles; Wanke, Christine; Gormley, Joan; Marcus, Cheryl J.; Putnam, Beverly; Loeliger, Edde; Pappa, Keith A.; Webb, Nancy; Shugarts, David L.; Winters, Mark A.; Descallar, Renard S.; Steele, Joseph; Wulfsohn, Michael; Said, Farideh; Chen, Yue; Martin, John C; Bischofberger, Norbert; Cheng, Andrew; Jaffe, Howard; Sharma, Jabin; Poongulali, S.; Cardoso, Sandra Wagner; Faria, Deise Lucia; Berendes, Sima; Burke, Kelly; Mngqibisa, Rosie; Kanyama, Cecelia; Kayoyo, Virginia; Samaneka, Wadzanai P.; Chisada, Anthony; Faesen, Sharla; Chariyalertsak, Suwat; Santos, Breno; Lira, Rita Alves; Joglekar, Anjali A.; Rosa, Alberto La; Infante, Rosa; Jain, Mamta; Petersen, Tianna; Godbole, Sheela; Dhayarkar, Sampada; Feinberg, Judith; Baer, Jenifer; Pollard, Richard B.; Asmuth, David; Gangakhedkar, Raman R; Gaikwad, Asmita; Ray, M. Graham; Basler, Cathi; Para, Michael F.; Watson, Kathy J.; Taiwo, Babafemi; McGregor, Donna; Balfour, Henry H.; Mullan, Beth; Kim, Ge-Youl; Klebert, Michael K.; Cox, Gary Matthew; Silberman, Martha; Mildvan, Donna; Revuelta, Manuel; Tashima, Karen T.; Patterson, Helen; Geiseler, P. Jan; Santos, Bartolo; Daar, Eric S; Lopez, Ruben; Frarey, Laurie; Currin, David; Haas, David H.; Bailey, Vicki L.; Tebas, Pablo; Zifchak, Larisa; Noel-Connor, Jolene; Torres, Madeline; Sha, Beverly E.; Fritsche, Janice M.; Cespedes, Michelle; Forcht, Janet; O'Brien, William A.; Mogridge, Cheryl; Hurley, Christine; Corales, Roberto; Palmer, Maria; Adams, Mary; Luque, Amneris; Lopez-Detres, Luis; Stroberg, Todd

    2012-01-01

    Background Antiretroviral regimens with simplified dosing and better safety are needed to maximize the efficiency of antiretroviral delivery in resource-limited settings. We investigated the efficacy and safety of antiretroviral regimens with once-daily compared to twice-daily dosing in diverse areas of the world. Methods and Findings 1,571 HIV-1-infected persons (47% women) from nine countries in four continents were assigned with equal probability to open-label antiretroviral therapy with efavirenz plus lamivudine-zidovudine (EFV+3TC-ZDV), atazanavir plus didanosine-EC plus emtricitabine (ATV+DDI+FTC), or efavirenz plus emtricitabine-tenofovir-disoproxil fumarate (DF) (EFV+FTC-TDF). ATV+DDI+FTC and EFV+FTC-TDF were hypothesized to be non-inferior to EFV+3TC-ZDV if the upper one-sided 95% confidence bound for the hazard ratio (HR) was ≤1.35 when 30% of participants had treatment failure. An independent monitoring board recommended stopping study follow-up prior to accumulation of 472 treatment failures. Comparing EFV+FTC-TDF to EFV+3TC-ZDV, during a median 184 wk of follow-up there were 95 treatment failures (18%) among 526 participants versus 98 failures among 519 participants (19%; HR 0.95, 95% CI 0.72–1.27; p = 0.74). Safety endpoints occurred in 243 (46%) participants assigned to EFV+FTC-TDF versus 313 (60%) assigned to EFV+3TC-ZDV (HR 0.64, CI 0.54–0.76; p<0.001) and there was a significant interaction between sex and regimen safety (HR 0.50, CI 0.39–0.64 for women; HR 0.79, CI 0.62–1.00 for men; p = 0.01). Comparing ATV+DDI+FTC to EFV+3TC-ZDV, during a median follow-up of 81 wk there were 108 failures (21%) among 526 participants assigned to ATV+DDI+FTC and 76 (15%) among 519 participants assigned to EFV+3TC-ZDV (HR 1.51, CI 1.12–2.04; p = 0.007). Conclusion EFV+FTC-TDF had similar high efficacy compared to EFV+3TC-ZDV in this trial population, recruited in diverse multinational settings. Superior safety, especially in HIV-1-infected

  6. Efficacy and safety of three antiretroviral regimens for initial treatment of HIV-1: a randomized clinical trial in diverse multinational settings.

    Directory of Open Access Journals (Sweden)

    Thomas B Campbell

    Full Text Available Antiretroviral regimens with simplified dosing and better safety are needed to maximize the efficiency of antiretroviral delivery in resource-limited settings. We investigated the efficacy and safety of antiretroviral regimens with once-daily compared to twice-daily dosing in diverse areas of the world.1,571 HIV-1-infected persons (47% women from nine countries in four continents were assigned with equal probability to open-label antiretroviral therapy with efavirenz plus lamivudine-zidovudine (EFV+3TC-ZDV, atazanavir plus didanosine-EC plus emtricitabine (ATV+DDI+FTC, or efavirenz plus emtricitabine-tenofovir-disoproxil fumarate (DF (EFV+FTC-TDF. ATV+DDI+FTC and EFV+FTC-TDF were hypothesized to be non-inferior to EFV+3TC-ZDV if the upper one-sided 95% confidence bound for the hazard ratio (HR was ≤1.35 when 30% of participants had treatment failure. An independent monitoring board recommended stopping study follow-up prior to accumulation of 472 treatment failures. Comparing EFV+FTC-TDF to EFV+3TC-ZDV, during a median 184 wk of follow-up there were 95 treatment failures (18% among 526 participants versus 98 failures among 519 participants (19%; HR 0.95, 95% CI 0.72-1.27; p = 0.74. Safety endpoints occurred in 243 (46% participants assigned to EFV+FTC-TDF versus 313 (60% assigned to EFV+3TC-ZDV (HR 0.64, CI 0.54-0.76; p<0.001 and there was a significant interaction between sex and regimen safety (HR 0.50, CI 0.39-0.64 for women; HR 0.79, CI 0.62-1.00 for men; p = 0.01. Comparing ATV+DDI+FTC to EFV+3TC-ZDV, during a median follow-up of 81 wk there were 108 failures (21% among 526 participants assigned to ATV+DDI+FTC and 76 (15% among 519 participants assigned to EFV+3TC-ZDV (HR 1.51, CI 1.12-2.04; p = 0.007.EFV+FTC-TDF had similar high efficacy compared to EFV+3TC-ZDV in this trial population, recruited in diverse multinational settings. Superior safety, especially in HIV-1-infected women, and once-daily dosing of EFV+FTC-TDF are

  7. Learning from safety in other industries

    NARCIS (Netherlands)

    Terwel, K.C.; Zwaard, W

    2012-01-01

    The Dutch building industry has been shocked by some major structural accidents during the last 10 years with buildings during construction as well as with delivered buildings. Several initiatives were started to improve the safety. In other industries the safety awareness seemed to be more

  8. Safety strategy and safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1976-01-01

    The safety strategy for nuclear power plants is characterized by the fact that the high level of safety was attained not as a result of experience, but on the basis of preventive accident analyses and the finding derived from such analyses. Although, in these accident analyses, the deterministic approach is predominant, it is supplemented by reliability analyses. The accidents analyzed in nuclear licensing procedures cover a wide spectrum from minor incidents to the design basis accidents which determine the design of the safety devices. The initial and boundary conditions, which are essentail for accident analyses, and the determination of the loads occurring in various states during regular operation and in accidents flow into the design of the individual systems and components. The inevitable residual risk and its origins are discussed. (orig.) [de

  9. Evaluation of different fracture-mechanical J-integral initiation values with regard to their usability in the safety assessment of components

    International Nuclear Information System (INIS)

    Eisele, U.; Roos, E.

    1991-01-01

    Determining fracture-mechanical material characteristic values on the basis of the J-integral is described and stipulated in a variety of standards and guidelines. The individual specifications differ in terms of procedure when determining the characteristic values and, therefore, also in terms of the meaningfulness of the results. This paper presents the different procedures, suggested in the course of the development of test methods in the field of elastic-plastic fracture mechanics, used to characterize crack initiation behaviour with regard to their features as material characteristic values and their usability in the safety assessment of components. (orig.)

  10. A methodology for analyzing precursors to earthquake-initiated and fire-initiated accident sequences

    International Nuclear Information System (INIS)

    Budnitz, R.J.; Lambert, H.E.; Apostolakis, G.

    1998-04-01

    This report covers work to develop a methodology for analyzing precursors to both earthquake-initiated and fire-initiated accidents at commercial nuclear power plants. Currently, the U.S. Nuclear Regulatory Commission sponsors a large ongoing project, the Accident Sequence Precursor project, to analyze the safety significance of other types of accident precursors, such as those arising from internally-initiated transients and pipe breaks, but earthquakes and fires are not within the current scope. The results of this project are that: (1) an overall step-by-step methodology has been developed for precursors to both fire-initiated and seismic-initiated potential accidents; (2) some stylized case-study examples are provided to demonstrate how the fully-developed methodology works in practice, and (3) a generic seismic-fragility date base for equipment is provided for use in seismic-precursors analyses. 44 refs., 23 figs., 16 tabs

  11. Nuclear Safety Charter; Charte Surete Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and

  12. Progesterone for the prevention of preterm birth: indications, when to initiate, efficacy and safety

    Directory of Open Access Journals (Sweden)

    Helen Y How

    2008-12-01

    Full Text Available Helen Y How, Baha M SibaiDivision of Maternal Fetal Medicine, Department of Obstetrics and Gynecology, University of Cincinnati, Cincinnati, OH USAAbstract: Preterm birth is the leading cause of neonatal mortality and morbidity and long-term disability of non-anomalous infants. Previous studies have identified a prior early spontaneous preterm birth as the risk factor with the highest predictive value for recurrence. Two recent double blind randomized placebo controlled trials reported lower preterm birth rate with the use of either intramuscular 17 alpha-hydroxyprogesterone caproate (IM 17OHP-C or intravaginal micronized progesterone suppositories in women at risk for preterm delivery. However, it is still unclear which high-risk women would truly benefit from this treatment in a general clinical setting and whether socio-cultural, racial and genetic differences play a role in patient’s response to supplemental progesterone. In addition the patient’s acceptance of such recommendation is also in question. More research is still required on identification of at risk group, the optimal gestational age at initiation, mode of administration, dose of progesterone and long-term safety.Keywords: preterm birth prevention, 17-alpha-hydroxyprogesterone caproate

  13. Design, production and initial state of the canister

    International Nuclear Information System (INIS)

    Cederqvist, Lars; Johansson, Magnus; Leskinen, Nina; Ronneteg, Ulf

    2010-12-01

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility.The report provides input on the initial state of the canisters to the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides input to the operational safety report, SR-Operation, on how the canisters shall be handled and disposed. The report presents the design premises and reference design of the canister and verifies the conformity of the reference design to the design premises. The production methods and the ability to produce canisters according to the reference design are described. Finally, the initial state of the canisters and their conformity to the reference design and design premises are presented

  14. Design, production and initial state of the canister

    Energy Technology Data Exchange (ETDEWEB)

    Cederqvist, Lars; Johansson, Magnus; Leskinen, Nina; Ronneteg, Ulf

    2010-12-15

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility.The report provides input on the initial state of the canisters to the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides input to the operational safety report, SR-Operation, on how the canisters shall be handled and disposed. The report presents the design premises and reference design of the canister and verifies the conformity of the reference design to the design premises. The production methods and the ability to produce canisters according to the reference design are described. Finally, the initial state of the canisters and their conformity to the reference design and design premises are presented

  15. Design, production and initial state of the closure

    International Nuclear Information System (INIS)

    2010-12-01

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The production reports are included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the closure and plugs in underground openings other than deposition tunnels for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides some input to the operational safety report, SR-Operation, on how the closure and plugs shall be handled and installed. The report presents the design premises and reference designs of the closure and plugs and verifies their conformity to the design premises. It also briefly deals with the production of the closure and plugs. Finally, the initial state of the closure and plugs and their conformity to the reference designs and design premises are presented

  16. Design, production and initial state of the closure

    Energy Technology Data Exchange (ETDEWEB)

    2010-12-15

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The production reports are included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the closure and plugs in underground openings other than deposition tunnels for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides some input to the operational safety report, SR-Operation, on how the closure and plugs shall be handled and installed. The report presents the design premises and reference designs of the closure and plugs and verifies their conformity to the design premises. It also briefly deals with the production of the closure and plugs. Finally, the initial state of the closure and plugs and their conformity to the reference designs and design premises are presented

  17. Design, production and initial state of the buffer

    Energy Technology Data Exchange (ETDEWEB)

    Boerjesson, Lennart; Gunnarsson, David; Johannesson, Lars-Erik; Jonsson, Esther

    2010-12-15

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the buffer for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides input to the operational safety report, SR-Operation, on how the buffer shall be handled and installed. The report presents the design premises and reference design of the buffer and verifies the conformity of the reference design to the design premises. It also describes the production of the buffer, from excavation and delivery of buffer material to installation in the deposition hole. Finally, the initial state of the buffer and its conformity to the reference design and design premises is presented

  18. Initiating Event Analysis of a Lithium Fluoride Thorium Reactor

    Science.gov (United States)

    Geraci, Nicholas Charles

    The primary purpose of this study is to perform an Initiating Event Analysis for a Lithium Fluoride Thorium Reactor (LFTR) as the first step of a Probabilistic Safety Assessment (PSA). The major objective of the research is to compile a list of key initiating events capable of resulting in failure of safety systems and release of radioactive material from the LFTR. Due to the complex interactions between engineering design, component reliability and human reliability, probabilistic safety assessments are most useful when the scope is limited to a single reactor plant. Thus, this thesis will study the LFTR design proposed by Flibe Energy. An October 2015 Electric Power Research Institute report on the Flibe Energy LFTR asked "what-if?" questions of subject matter experts and compiled a list of key hazards with the most significant consequences to the safety or integrity of the LFTR. The potential exists for unforeseen hazards to pose additional risk for the LFTR, but the scope of this thesis is limited to evaluation of those key hazards already identified by Flibe Energy. These key hazards are the starting point for the Initiating Event Analysis performed in this thesis. Engineering evaluation and technical study of the plant using a literature review and comparison to reference technology revealed four hazards with high potential to cause reactor core damage. To determine the initiating events resulting in realization of these four hazards, reference was made to previous PSAs and existing NRC and EPRI initiating event lists. Finally, fault tree and event tree analyses were conducted, completing the logical classification of initiating events. Results are qualitative as opposed to quantitative due to the early stages of system design descriptions and lack of operating experience or data for the LFTR. In summary, this thesis analyzes initiating events using previous research and inductive and deductive reasoning through traditional risk management techniques to

  19. Consideration of future safety consequences: a new predictor of employee safety.

    Science.gov (United States)

    Probst, Tahira M; Graso, Maja; Estrada, Armando X; Greer, Sarah

    2013-06-01

    Compliance with safety behaviors is often associated with longer term benefits, but may require some short-term sacrifices. This study examines the extent to which consideration of future safety consequences (CFSC) predicts employee safety outcomes. Two field studies were conducted to evaluate the reliability and validity of the newly developed Consideration of Future Safety Consequences (CFSC) scale. Surveys containing the CFSC scale and other measures of safety attitudes, behaviors, and outcomes were administered during working hours to a sample of 128 pulp and paper mill employees; after revising the CFSC scale based on these initial results, follow-up survey data were collected in a second sample of 212 copper miners. In Study I, CFSC was predictive of employee safety knowledge and motivation, compliance, safety citizenship behaviors, accident reporting attitudes and behaviors, and workplace injuries - even after accounting for conscientiousness and demographic variables. Moreover, the effects of CFSC on the variables generally appear to be direct, as opposed to mediated by safety knowledge or motivation. These findings were largely replicated in Study II. CFSC appears to be an important personality construct that may predict those individuals who are more likely to comply with safety rules and have more positive safety outcomes. Future research should examine the longitudinal stability of CFSC to determine the extent to which this construct is a stable trait, rather than a safety attitude amenable to change over time or following an intervention. Copyright © 2013 Elsevier Ltd. All rights reserved.

  20. Multimegawatt Space Reactor Safety

    International Nuclear Information System (INIS)

    Stanley, M.L.

    1989-01-01

    The Multimegawatt (MMW) Space Reactor Project supports the Strategic Defense Initiative Office requirement to provide reliable, safe, cost-effective, electrical power in the MMW range. Specifically, power may be used for neutral particle beams, free electron lasers, electromagnetic launchers, and orbital transfer vehicles. This power plant technology may also apply to the electrical power required for other uses such as deep-space probes and planetary exploration. The Multimegawatt Space Reactor Project, the Thermionic Fuel Element Verification Program, and Centaurus Program all support the Multimegawatt Space Nuclear Power Program and form an important part of the US Department of Energy's (DOE's) space and defense power systems activities. A major objective of the MMW project is the development of a reference flight system design that provides the desired levels of public safety, health protection, and special nuclear material (SNM) protection when used during its designated missions. The safety requirements for the MMW project are a hierarchy of requirements that consist of safety requirements/regulations, a safety policy, general safety criteria, safety technical specifications, safety design specifications, and the system design. This paper describes the strategy and philosophy behind the development of the safety requirements imposed upon the MMW concept developers. The safety organization, safety policy, generic safety issues, general safety criteria, and the safety technical specifications are discussed

  1. Patient participation in patient safety and nursing input - a systematic review.

    Science.gov (United States)

    Vaismoradi, Mojtaba; Jordan, Sue; Kangasniemi, Mari

    2015-03-01

    This systematic review aims to synthesise the existing research on how patients participate in patient safety initiatives. Ambiguities remain about how patients participate in routine measures designed to promote patient safety. Systematic review using integrative methods. Electronic databases were searched using keywords describing patient involvement, nursing input and patient safety initiatives to retrieve empirical research published between 2007 and 2013. Findings were synthesized using the theoretical domains of Vincent's framework for analysing risk and safety in clinical practice: "patient", "healthcare provider", "task", "work environment", "organisation & management". We identified 17 empirical research papers: four qualitative, one mixed-method and 12 quantitative designs. All 17 papers indicated that patients can participate in safety initiatives. Improving patient participation in patient safety necessitates considering the patient as a person, the nurse as healthcare provider, the task of participation and the clinical environment. Patients' knowledge, health conditions, beliefs and experiences influence their decisions to engage in patient safety initiatives. An important component of the management of long-term conditions is to ensure that patients have sufficient knowledge to participate. Healthcare providers may need further professional development in patient education and patient care management to promote patient involvement in patient safety, and ensure that patients understand that they are 'allowed' to inform nurses of adverse events or errors. A healthcare system characterised by patient-centredness and mutual acknowledgement will support patient participation in safety practices. Further research is required to improve international knowledge of patient participation in patient safety in different disciplines, contexts and cultures. Patients have a significant role to play in enhancing their own safety while receiving hospital care. This

  2. Safety design concept and analysis for the upgrading JRR-3

    International Nuclear Information System (INIS)

    Onishi, N.; Isshiki, M.; Takahashi, H.; Takayanagi, M.

    1990-01-01

    The Research Reactor No.3 (JRR-3) is under reconstruction for upgrading. This paper describes the safety design concepts of the architectural and engineering design, anticipated operational transients and accident conditions which are the postulated initiating events for the safety evaluation, and the safety criteria of the upgraded JRR-3. The safety criteria are defined taking into account those of Light Water Reactors and the characteristics of the research reactor. Using the example of the safety analysis, this paper describes analytical results of a reactivity insertion by removal of in-core irradiation samples, a pipeline break at the primary coolant loop and flow blockage to a coolant channel, which are the severest postulated initiating events of the JRR-3

  3. Understanding the value of mixed methods research: the Children’s Safety Initiative-Emergency Medical Services

    Science.gov (United States)

    Hansen, Matthew; O’Brien, Kerth; Meckler, Garth; Chang, Anna Marie; Guise, Jeanne-Marie

    2016-01-01

    Mixed methods research has significant potential to broaden the scope of emergency care and specifically emergency medical services investigation. Mixed methods studies involve the coordinated use of qualitative and quantitative research approaches to gain a fuller understanding of practice. By combining what is learnt from multiple methods, these approaches can help to characterise complex healthcare systems, identify the mechanisms of complex problems such as medical errors and understand aspects of human interaction such as communication, behaviour and team performance. Mixed methods approaches may be particularly useful for out-of-hospital care researchers because care is provided in complex systems where equipment, interpersonal interactions, societal norms, environment and other factors influence patient outcomes. The overall objectives of this paper are to (1) introduce the fundamental concepts and approaches of mixed methods research and (2) describe the interrelation and complementary features of the quantitative and qualitative components of mixed methods studies using specific examples from the Children’s Safety Initiative-Emergency Medical Services (CSI-EMS), a large National Institutes of Health-funded research project conducted in the USA. PMID:26949970

  4. PROPOSAL OF VOIVODESHIP ROAD SAFETY IMPROVEMENT PROGRAMME

    OpenAIRE

    Tomasz SZCZURASZEK; Jan KEMPA

    2016-01-01

    The article presents a proposal of the ‘GAMBIT KUJAWSKO-POMORSKI’ Road Safety Improvement Programme. The main idea of the Programme is to establish and initiate systems that will be responsible for the most important areas of activity within road safety, including road safety control, supervision, and management systems in the whole Voivodeship. In total, the creation and start of nine such systems has been proposed, namely: the Road Safety Management, the Integrated Road Rescue Service, the ...

  5. Space reactor safety, 1985--1995 lessons learned

    International Nuclear Information System (INIS)

    Marshall, A.C.

    1995-01-01

    Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration

  6. Space reactor safety, 1985--1995 lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, A.C.

    1995-12-31

    Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration.

  7. Operational safety at the FFTF

    International Nuclear Information System (INIS)

    Baird, Q.L.; Hagan, J.W.; Seeman, S.E.; Baker, S.M.

    1981-02-01

    An extensive operational nuclear safety program has been an integral part of the design, startup, and initial operating phases of the Fast Flux Test Facility (FFTF). During the design and construction of the facility, a program of independent safety overviews and analyses assured the provision of responsible safety margins within the plant, protective systems, and engineered safety features for protection of the public, operating staff, and the facility. The program is continuing through surveillance of operations to verify continued adherence to the established operating envelope and for timely identification of any trends potentially adverse to those margins. Experience from operation of FFTF is being utilized in the development of enhanced operational nuclear safety aids for application in follow-on breeder reactor power systems. The commendable plant and personnel safety experiences of FFTF through its startup and ascension to full power demonstrate the overall effectiveness of the FFTF operational nuclear safety program

  8. Safety culture assessment developed by JANTI

    International Nuclear Information System (INIS)

    Hamada, Jun

    2009-01-01

    Japan's JCO accident in September 1999 provided a real-life example of what can happen when insufficient attention is paid to safety culture. This accident brought to light the importance of safety culture and reinforced the movement to foster a safety culture. Despite this, accidents and inappropriate conduct have continued to occur. Therefore, there is a strong demand to instill a safety culture throughout the nuclear power industry. In this context, Japan's nuclear power regulator, the Nuclear and Industrial Safety Agency (NISA), decided to include in its safety inspections assessments of the safety culture found in power utilities' routine safety operations to get signs of deterioration in the organizational climate. In 2007, NISA constructed guidelines for their inspectors to carry out these assessments. At the same time, utilities have embarked on their own independent safety culture initiatives, such as revising their technical specifications and building effective PDCA cycle to promote safety culture. In concert with these developments, JANTI has also instituted safety culture assessments. (author)

  9. A report on developing a checklist to assess company plans focused on improving safety awareness, safe behaviour and safety culture: final report

    NARCIS (Netherlands)

    Steijger, N.; Starren, H.; Keus, M.; Gort, J.; Vervoort, M.

    2003-01-01

    This report describes the process of developing a checklist to asses company plans focused on improving safety awareness, safe behaviour and safety culture. These plans are part of a programme initiated by the Ministry of Social Affairs and Employment aiming at improving the safety performance of

  10. PATIENT SAFETY IN SURGERY: THE QUALITY OF IMPLEMENTATION OF PATIENT SAFETY CHECKLISTS IN A REGIONAL HOSPITAL

    Directory of Open Access Journals (Sweden)

    V. Karyadinata

    2012-09-01

    Full Text Available Introduction. Patient safety and the avoidance of inhospital adverse events is a key focus of clinical practice and medical audit. A large of proportion of medical errors affect surgical patients in the peri-operative setting. Safety checklists have been adopted by the medical profession from the aviation industry as a cheap and reliable method of avoiding errors which arise from complex or stressful situations. Current evidence suggests that the use of periooperative checklists has led to a decrease in surgical morbidity and hospital costs. Aim. To assess the quality of implementation of a modified patient safety checklist in a UK district general hospital. Methods. An observational tool was designed to assess in real time the peri-operative performance of the surgical safety checklist in patients undergoing general surgical, urological or orthopaedic procedures. Initiation of the checklist, duration of performance and staff participation were audited in real time. Results. 338 cases were monitored. Nurses were most active in initiating the safety checklist. The checklist was performed successfully in less than a minute in most cases. 11-24% of staff (according to professional group present in the operating room did not participate in the checklist. Critical safety checks (patient identity and procedure name were performed in all cases across all specialties. Variations were noted in checking other categories, such as deep vein thrombosis (DVT prophylaxis or patient warming. Conclusions. There is still a potential for improving the practice and culture of surgical patient safety activities. Staff training and designation of patient safety leadership roles is needed in increasing compliance and implementation of patient safety mechanism, such as peri-operative checklists. There is significant data to advocate the need to implement patient safety surgical checklists internationally

  11. Dicty_cDB: VHE123 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available nificant alignments: (bits) Value (Q9NZJ4) RecName: Full=Sacsin; &AL157766_4( AL157766 |pid:none) 105 4e-21 ...none) Micromonas sp. RCC299 chromosome... 103 1e-20 BC138482_1( BC138482 |pid:none) Mus musculus sacsi...n, mRNA (cDNA cl... 103 1e-20 (Q9JLC8) RecName: Full=Sacsin; 103 1e-20 BC171956_1( BC17...1956 |pid:none) Mus musculus sacsin, mRNA (cDNA cl... 103 1e-20 AB006708_10( AB006708 |pid:none) Arabidopsis

  12. Patient safety and nutrition: is there a connection? | Nieuwoudt ...

    African Journals Online (AJOL)

    Nutrition care is not always recognised as a patient safety issue. This article explores the origins of the patient safety initiative and seeks to identify possible connections between nutrition care and patient safety. Examples of tools that can be used to improve the safety of nutrition care are provided. This is also a call to action ...

  13. [A simplified occupational health and safety management system designed for small enterprises. Initial validation results].

    Science.gov (United States)

    Bacchi, Romana; Veneri, L; Ghini, P; Caso, Maria Alessandra; Baldassarri, Giovanna; Renzetti, F; Santarelli, R

    2009-01-01

    Occupational Health and Safety Management Systems (OHSMS) are known to be effective in improving safety at work. Unfortunately they are often too resource-heavy for small businesses. The aim of this project was to develop and test a simplified model of OHSMS suitable for small enterprises. The model consists of 7 procedures and various operating forms and check lists, that guide the enterprise in managing safety at work. The model was tested in 15 volunteer enterprises. In most of the enterprises two audits showed increased awareness and participation of workers; better definition and formalisation of respon sibilities in 8 firms; election of Union Safety Representatives in over one quarter of the enterprises; improvement of safety equipment. The study also helped identify areas where the model could be improved by simplification of unnecessarily complex and redundant procedures.

  14. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  15. Safety Analysis of Stochastic Dynamical Systems

    DEFF Research Database (Denmark)

    Sloth, Christoffer; Wisniewski, Rafael

    2015-01-01

    This paper presents a method for verifying the safety of a stochastic system. In particular, we show how to compute the largest set of initial conditions such that a given stochastic system is safe with probability p. To compute the set of initial conditions we rely on the moment method that via...... that shows how the p-safe initial set is computed numerically....

  16. Survey and analysis of radiation safety management systems at medical institutions. Initial report. Radiation protection supervisor, radiation safety organization, and education and training

    International Nuclear Information System (INIS)

    Ohba, Hisateru; Ogasawara, Katsuhiko; Aburano, Tamio

    2005-01-01

    In this study, a questionnaire survey was carried out to determine the actual situation of radiation safety management systems in Japanese medical institutions with nuclear medicine facilities. The questionnaire consisted of questions concerning the Radiation Protection Supervisor license, safety management organizations, and problems related to education and training in safety management. Analysis was conducted according to region, type of establishment, and number of beds. The overall response rate was 60%, and no significant difference in response rate was found among regions. Medical institutions that performed nuclear medicine practices without a radiologist participating accounted for 10% of the total. Medical institutions where nurses gave patients intravenous injections of radiopharmaceuticals as part of the nuclear medicine practices accounted for 28% of the total. Of these medical institutions, 59% provided education and training in safety management for nurses. The rate of acquisition of Radiation Protection Supervisor licenses was approximately 70% for radiological technologists and approximately 20% for physicians (regional difference, p=0.02). The rate of medical institutions with safety management organizations was 71% of the total. Among the medical institutions (n=208) without safety management organizations, approximately 56% had 300 beds or fewer. In addition, it became clear that 35% of quasi-public organizations and 44% of private organizations did not provide education and training in safety management (p<0.001, according to establishment). (author)

  17. The international state of affairs in marine safety

    International Nuclear Information System (INIS)

    Benkert, W.M.

    1978-01-01

    The three-fold objective of marine safety is examined with emphasis on international cooperation as a means of achievement. In this respect, the recent and present activities of the Intergovernmental Maritime Consultative organization are reviewed by looking at the accomplishments and goals of several subcommittees of the Maritime Safety Committee. The United States program for commercial vessel safety is briefly discussed along with a comment on the recent Tanker Safety initiatives

  18. Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

    2008-07-01

    'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

  19. Nuclear safety education and training network

    International Nuclear Information System (INIS)

    Bastos, J.; Ulfkjaer, L.

    2004-01-01

    In March 2001, the Secretariat convened an Advisory Group on Education and Training in nuclear safety. The Advisory Group considered structure, scope and means related to the implementation of an IAEA Programme on Education and Training . A strategic plan was agreed and the following outputs were envisaged: 1. A Training Support Programme in nuclear safety, including a standardized and harmonized approach for training developed by the IAEA and in use by Member States. 2. National and regional training centres, established to support sustainable national nuclear safety infrastructures. 3. Training material for use by lecturers and students developed by the IAEA in English and translated to other languages. The implementation of the plan was initiated in 2002 emphasizing the preparation of training materials. In 2003 a pilot project for a network on Education and Training in Asia was initiated

  20. Chemical Hazards and Safety Issues in Fusion Safety Design

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    2003-01-01

    Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

  1. Exploring relationships between hospital patient safety culture and Consumer Reports safety scores.

    Science.gov (United States)

    Smith, Scott Alan; Yount, Naomi; Sorra, Joann

    2017-02-16

    A number of private and public companies calculate and publish proprietary hospital patient safety scores based on publicly available quality measures initially reported by the U.S. federal government. This study examines whether patient safety culture perceptions of U.S. hospital staff in a large national survey are related to publicly reported patient safety ratings of hospitals. The Agency for Healthcare Research and Quality Hospital Survey on Patient Safety Culture (Hospital SOPS) assesses provider and staff perceptions of hospital patient safety culture. Consumer Reports (CR), a U.S. based non-profit organization, calculates and shares with its subscribers a Hospital Safety Score calculated annually from patient experience survey data and outcomes data gathered from federal databases. Linking data collected during similar time periods, we analyzed relationships between staff perceptions of patient safety culture composites and the CR Hospital Safety Score and its five components using multiple multivariate linear regressions. We analyzed data from 164 hospitals, with patient safety culture survey responses from 140,316 providers and staff, with an average of 856 completed surveys per hospital and an average response rate per hospital of 56%. Higher overall Hospital SOPS composite average scores were significantly associated with higher overall CR Hospital Safety Scores (β = 0.24, p Consumer Reports Hospital Safety Score, which is a composite of patient experience and outcomes data from federal databases. As hospital managers allocate resources to improve patient safety culture within their organizations, their efforts may also indirectly improve consumer-focused, publicly reported hospital rating scores like the Consumer Reports Hospital Safety Score.

  2. Safety logic systems of PFBR

    International Nuclear Information System (INIS)

    Sambasivan, S. Ilango

    2004-01-01

    Full text : PFBR is provided with two independent, fast acting and diverse shutdown systems to detect any abnormalities and to initiate safety action. Each system consists of sensors, signal processing systems, logics, drive mechanisms and absorber rods. The absorber rods of the first system are Control and Safety Rods (CSR) and that of the second are called as Diverse Safety Rods (DSR). There are nine CSR and three DSR. While CSR are used for startup, control of reactor power, controlled shutdown and SCRAM, the DSR are used only for SCRAM. The respective drive mechanisms are called as CSRDM and DSRDM. Each of these two systems is capable of executing the shutdown satisfactorily with single failure criteria. Two independent safety logic systems based on diverse principles have been designed for the two shut down systems. The analog outputs of the sensors of Core Monitoring Systems comprising of reactor flux monitoring, core temperature monitoring, failed fuel detection and core flow monitoring systems are processed and converted into binary signals depending on their instantaneous values. Safety logic systems receive the binary signals from these core-monitoring systems and process them logically to protect the reactor against postulated initiating events. Neutronic and power to flow (P/Q) signals form the inputs to safety logic system-I and temperature signals are inputs to the safety logic system II. Failed fuel detection signals are processed by both the shut down systems. The two logic systems to actuate the safety rods are also based on two diverse designs and implemented with solid-state devices to meet all the requirements of safety systems. Safety logic system I that caters to neutronic and P/Q signals is designed around combinational logic and has an on-line test facility to detect struck at faults. The second logic system is based on dynamic logic and hence is inherently safe. This paper gives an overview of the two logic systems that have been

  3. Autonomous system for launch vehicle range safety

    Science.gov (United States)

    Ferrell, Bob; Haley, Sam

    2001-02-01

    The Autonomous Flight Safety System (AFSS) is a launch vehicle subsystem whose ultimate goal is an autonomous capability to assure range safety (people and valuable resources), flight personnel safety, flight assets safety (recovery of valuable vehicles and cargo), and global coverage with a dramatic simplification of range infrastructure. The AFSS is capable of determining current vehicle position and predicting the impact point with respect to flight restriction zones. Additionally, it is able to discern whether or not the launch vehicle is an immediate threat to public safety, and initiate the appropriate range safety response. These features provide for a dramatic cost reduction in range operations and improved reliability of mission success. .

  4. MR cholangiopancreatography in children: feasibility, safety, and initial experience

    International Nuclear Information System (INIS)

    Delaney, Lisa; Karmazyn, Boaz; Akisik, M.F.; Jennings, S.G.; Applegate, Kimberly E.

    2008-01-01

    The indications for MR cholangiopancreatography (MRCP) in children, and its safety and findings, might differ from those in adults and are not well described. To investigate the safety, feasibility, and accuracy of MRCP in children. We reviewed all prospective MRCP reports, noting the indication, the use of secretin, endoscopic retrograde cholangiopancreatography (ERCP) findings, and patient outcomes. Two readers reviewed each MRCP study by consensus to rate duct visualization and compare pancreatic duct sizes before and after secretin administration (paired t-test). The likelihood of a normal versus an abnormal MRCP study was compared by gender, pancreatitis as the primary indication, secretin use, and whether ERCP was performed (Fisher's exact test), as well as age (t-test). A total of 85 MRCP studies were performed in children (mean age 10.3 years), most commonly for evaluation of pancreatitis (n=47, 55%); 41 (48%) used secretin and 39 (46%) used a negative oral contrast agent. Of the 85 studies, 72 (85%) had excellent image quality and 43 were normal. ERCP was performed after 16 of the 85 MRCP studies (19%); the diagnoses were concordant with those of MRCP in 13 (81%). There were 42 abnormal MRCP studies, and these were more likely to be in girls (P=0.03) and in children who had undergone ERCP (P<0.01). Secretin and the negative oral contrast agent were well-tolerated. Secretin improved duct visualization (P<0.001). MRCP safely and accurately depicted pancreaticobiliary anatomy in children. The use of secretin improved visualization of the pancreatic duct. (orig.)

  5. Safety management - policy, analysis and implementation

    International Nuclear Information System (INIS)

    Allen, F.R.

    1993-01-01

    The nuclear industry is moving towards a period of ever increasing emphasis on business performance and profitability. Safety has, of course, always been a major concern of management in the nuclear industry and elsewhere. The civil aviation industry , for example, has had a similar concern for safety. Other industry sectors are also developing safety management as a response to events within and outside their sectors. In this paper the way that the risk management process as a whole is being addressed is looked at. Can we use risk management, initially a safety-orientated tool, to improve business performance? (author)

  6. Development and implementation of setpoint tolerances for special safety systems

    International Nuclear Information System (INIS)

    Oliva, A.F.; Balog, G.; Parkinson, D.G.; Archinoff, G.H.

    1991-01-01

    The establishment of tolerances and impairment limits for special safety system setpoints is part of the process whereby the plant operator demonstrates to the regulatory authority that the plant operates safely and within the defined plant licensing envelope. The licensing envelope represents the set of limits and plant operating state and for which acceptably safe plant operation has been demonstrated by the safety analysis. By definition, operation beyond this envelope contributes to overall safety system unavailability. Definition of the licensing envelope is provided in a wide range of documents including the plant operating licence, the safety report, and the plant operating policies and principles documents. As part of the safety analysis, limits are derived for each special safety system initiating parameter such that the relevant safety design objectives are achieved for all design basis events. If initiation on a given parameter occurs at a level beyond its limit, there is a potential reduction in safety system effectiveness relative to the performance credited in the plant safety analysis. These safety system parameter limits, when corrected for random and systematic instrument errors and other errors inherent in the process of periodic testing or calibration, are then used to derive parameter impairment levels and setpoint tolerances. This paper describes the methodology that has evolved at Ontario Hydro for developing and implementing tolerances for special safety system parameters (i.e., the shutdown systems, emergency coolant injection system and containment system). Tolerances for special safety system initiation setpoints are addressed specifically, although many of the considerations discussed here will apply to performance limits for other safety system components. The first part of the paper deals with the approach that has been adopted for defining and establishing setpoint limits and tolerances. The remainder of the paper addresses operational

  7. The spirit of safety: oriental safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Kondo, J. [Science Council of Japan, Tokyo (Japan)

    1996-09-01

    Failure of a large system causes disasters. However, after an accident, the causes are frequently attributed to human error when the operators do not survive the accident. It might be difficult to prove that the real cause of the accident is human error. Process decision program chart (PDPC) would be a useful tool in indicating the causes of an accident since it can clearly show that if the operator made the correct choice, the safety of the system could be maintained. The case of the incident of the nuclear reactor at Mihama unit 2 is indicated by PDPC in which the sequence of events and the operations are indicated in this paper together with the safe operation. One can easily understand the cause of the incident and the way to avoid it. Also, PDPC for the Three Mile Island (TMI) accident is shown. Initially, in order to prevent an accident, mental training and safety culture is most important. The oriental safety culture based on Zentoism, a school of Buddhism is discussed. (orig.)

  8. The spirit of safety: oriental safety culture

    International Nuclear Information System (INIS)

    Kondo, J.

    1996-01-01

    Failure of a large system causes disasters. However, after an accident, the causes are frequently attributed to human error when the operators do not survive the accident. It might be difficult to prove that the real cause of the accident is human error. Process decision program chart (PDPC) would be a useful tool in indicating the causes of an accident since it can clearly show that if the operator made the correct choice, the safety of the system could be maintained. The case of the incident of the nuclear reactor at Mihama unit 2 is indicated by PDPC in which the sequence of events and the operations are indicated in this paper together with the safe operation. One can easily understand the cause of the incident and the way to avoid it. Also, PDPC for the Three Mile Island (TMI) accident is shown. Initially, in order to prevent an accident, mental training and safety culture is most important. The oriental safety culture based on Zentoism, a school of Buddhism is discussed. (orig.)

  9. A philosophy for space nuclear systems safety

    International Nuclear Information System (INIS)

    Marshall, A.C.

    1992-01-01

    The unique requirements and contraints of space nuclear systems require careful consideration in the development of a safety policy. The Nuclear Safety Policy Working Group (NSPWG) for the Space Exploration Initiative has proposed a hierarchical approach with safety policy at the top of the hierarchy. This policy allows safety requirements to be tailored to specific applications while still providing reassurance to regulators and the general public that the necessary measures have been taken to assure safe application of space nuclear systems. The safety policy used by the NSPWG is recommended for all space nuclear programs and missions

  10. 30 CFR 56.6502 - Safety fuse.

    Science.gov (United States)

    2010-07-01

    ... be cut and capped in dry locations. (e) Blasting caps shall be crimped to fuse only with implements... material are securely in place. (g) Safety fuse shall be ignited only with devices designed for that... initiation systems, igniter cord and connectors, or other nonelectric initiation systems shall be used...

  11. L-Band Digital Aeronautical Communications System Engineering - Initial Safety and Security Risk Assessment and Mitigation

    Science.gov (United States)

    Zelkin, Natalie; Henriksen, Stephen

    2011-01-01

    This document is being provided as part of ITT's NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract NNC05CA85C, Task 7: "New ATM Requirements--Future Communications, C-Band and L-Band Communications Standard Development." ITT has completed a safety hazard analysis providing a preliminary safety assessment for the proposed L-band (960 to 1164 MHz) terrestrial en route communications system. The assessment was performed following the guidelines outlined in the Federal Aviation Administration Safety Risk Management Guidance for System Acquisitions document. The safety analysis did not identify any hazards with an unacceptable risk, though a number of hazards with a medium risk were documented. This effort represents a preliminary safety hazard analysis and notes the triggers for risk reassessment. A detailed safety hazards analysis is recommended as a follow-on activity to assess particular components of the L-band communication system after the technology is chosen and system rollout timing is determined. The security risk analysis resulted in identifying main security threats to the proposed system as well as noting additional threats recommended for a future security analysis conducted at a later stage in the system development process. The document discusses various security controls, including those suggested in the COCR Version 2.0.

  12. Understanding the value of mixed methods research: the Children's Safety Initiative-Emergency Medical Services.

    Science.gov (United States)

    Hansen, Matthew; O'Brien, Kerth; Meckler, Garth; Chang, Anna Marie; Guise, Jeanne-Marie

    2016-07-01

    Mixed methods research has significant potential to broaden the scope of emergency care and specifically emergency medical services investigation. Mixed methods studies involve the coordinated use of qualitative and quantitative research approaches to gain a fuller understanding of practice. By combining what is learnt from multiple methods, these approaches can help to characterise complex healthcare systems, identify the mechanisms of complex problems such as medical errors and understand aspects of human interaction such as communication, behaviour and team performance. Mixed methods approaches may be particularly useful for out-of-hospital care researchers because care is provided in complex systems where equipment, interpersonal interactions, societal norms, environment and other factors influence patient outcomes. The overall objectives of this paper are to (1) introduce the fundamental concepts and approaches of mixed methods research and (2) describe the interrelation and complementary features of the quantitative and qualitative components of mixed methods studies using specific examples from the Children's Safety Initiative-Emergency Medical Services (CSI-EMS), a large National Institutes of Health-funded research project conducted in the USA. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

  13. Design, construction and initial state of the underground openings

    International Nuclear Information System (INIS)

    2010-12-01

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the underground openings for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the underground openings at final disposal, backfilling or closure. In addition, the report provides input to the operational safety report, SR-Operation, on how the underground openings shall be constructed and inspected. The report presents the design premises and the methodology applied to design the underground openings and adapt them the to the site conditions so that they conform to the design premises. It presents the reference design at Forsmark and its conformity to the design premises. It also describes the reference methods to be applied to construct and inspect the different kinds of underground openings. Finally, the initial state of the underground openings and its conformity to the design premises is presented

  14. Design, construction and initial state of the underground openings

    Energy Technology Data Exchange (ETDEWEB)

    2010-12-15

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the underground openings for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the underground openings at final disposal, backfilling or closure. In addition, the report provides input to the operational safety report, SR-Operation, on how the underground openings shall be constructed and inspected. The report presents the design premises and the methodology applied to design the underground openings and adapt them the to the site conditions so that they conform to the design premises. It presents the reference design at Forsmark and its conformity to the design premises. It also describes the reference methods to be applied to construct and inspect the different kinds of underground openings. Finally, the initial state of the underground openings and its conformity to the design premises is presented

  15. The initiating events in the Loviisa nuclear power plant history

    International Nuclear Information System (INIS)

    Sjoblom, K.

    1987-01-01

    During the 16 reactor years of Loviisa nuclear power plant operation no serious incident has endangered the high level of safety. The initiating events of plant incidents have been analyzed in order to get a view of plant operational safety experience. The initiating events have been placed in categories similar to those that EPRI uses. However, because of the very small number of scrams the study was extended to also cover transients with a relatively low safety importance in order to get more comprehensive statistics. Human errors, which contributed to 15% of the transients, were a special subject in this study. The conditions under which human failures occurred, and the nature and root causes of the human failures that caused the initiating events were analyzed. For future analyses it was noticed that it would be beneficial to analyze incidents immediately, to consult with the persons directly involved and to develop an international standard format for incident analyses

  16. Safety and environment

    International Nuclear Information System (INIS)

    Cogne, F.

    1975-01-01

    The author analyses the papers presented by C. Starr and M. Muntzing at the Paris Conference on the maturity of nuclear energy. The main problems raised in the matter of safety (safety of the plants, plutonium toxicity, the possibilities of theft or sabotage, treatment and storage of the waste) are analyzed and it is pointed out that the hazards arising from the use of nuclear power are contained within reasonable limits. The experts should take the initiative of informing the general public on these matters as the mass media circulate too much inaccurate information in this field. As concerns the environment, it is the choice of sites and the harmonizing of the rules and procedures which appear to be the most important problems for the authorities charged with safety measures [fr

  17. Radiation safety audit

    International Nuclear Information System (INIS)

    Kadadunna, K.P.I.K.; Mod Ali, Noriah

    2008-01-01

    Audit has been seen as one of the effective methods to ensure harmonization in radiation protection. A radiation safety audit is a formal safety performance examination of existing or future work activities by an independent team. Regular audit will assist the management in its mission to maintain the facilities environment that is inherently safe for its employees. The audits review the adequacy of facilities for the type of use, training, and competency of workers, supervision by authorized users, availability of survey instruments, security of radioactive materials, minimization of personnel exposure to radiation, safety equipment, and the required record keeping. All approved areas of use are included in these periodic audits. Any deficiency found in the audit shall be corrected as soon as possible after they are reported. Radiation safety audit is a proactive approach to improve radiation safety practices and identify and prevent any potential radiation accident. It is an excellent tool to identify potential problem to radiation users and to assure that safety measures to eliminate or reduce the problems are fully considered. Radiation safety audit will help to develop safety culture of the facility. It is intended to be the cornerstone of a safety program designed to aid the facility, staff and management in maintaining a safe environment in which activities are carried out. The initiative of this work is to evaluate the need of having a proper audit as one of the mechanism to manage the safety using ionizing radiation. This study is focused on the need of having a proper radiation safety audit to identify deviations and deficiencies of radiation protection programmes. It will be based on studies conducted on several institutes/radiation facilities in Malaysia in 2006. Steps will then be formulated towards strengthening radiation safety through proper audit. This will result in a better working situation and confidence in the radiation protection community

  18. Report of Committee for JAEA Internationalization Initiative

    International Nuclear Information System (INIS)

    2013-03-01

    In global circumstances surrounding nuclear energy, the role expected to Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has been promoted an initiative for the international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA established 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as the issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  19. Review of fuel safety criteria in France

    Energy Technology Data Exchange (ETDEWEB)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier [Institut de Radioprotection et du Surete Nucleaire, Fontenay-aux-Roses (France)

    2018-01-15

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  20. Review of fuel safety criteria in France

    International Nuclear Information System (INIS)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier

    2018-01-01

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  1. Reviewing the impact of organisational factors on nuclear power plants safety. A Spanish research initiative

    International Nuclear Information System (INIS)

    Sola, R.; Garces, M.I.; Vaquero, C.; Sendio, F.; De la Cal, C.; Villadoniga, J.I.

    2000-01-01

    This paper describes the Spanish R and D project 'Development of methods to evaluate and model the impact of organisation on nuclear power plants safety' framed in an specific agreement among UNESA (Association of Spanish Utilities), CSN (Spanish Nuclear Safety Council) and CIEMAT (Research Centre for Energy, Environment and Technology), being this last one the institution in charge of the development of the research activities. The main goal of the proposed project is to increase the knowledge related the way nuclear power plants organise and manage their activities to enhance safety. This goal will be achieved through three perspectives: the development of preventive and corrective methodologies and the development of models to incorporate the organisation and management in the probabilistic safety assessment, PSA. (author)

  2. Radiation Safety for Sustainable Development

    International Nuclear Information System (INIS)

    2015-10-01

    The objective of radiation safety is Assessments of Natural Radioactivity and its Radiological. The following topics were discussed during the conference: AFROSAFE Championing Radiation Safety in Africa, Radiation Calibration, and Development and Validation of a Laser Induced Breakdown Spectrometry Method for Cancer Detection and Characterization. Young Generation in NUCLEAR Initiative to Promote Nuclear Science and Technology, Radiation Protection Safety Culture and Application of Nuclear Techniques in Industry and the Environment were discuss. Rapid Chemometric X-Ray Fluorescence approaches for spectral Diagnostics of Cancer utilizing Tissue Trace Metals and Speciation profiles. Fundamental role of medical physics in Radiation Therapy

  3. Levels of safety

    International Nuclear Information System (INIS)

    Povyakalo, A.A.

    1996-01-01

    When speaking about danger of catastrophe, it is the first level of danger. Its absence is the first level of safety. When speaking about danger of danger of catastrophe, it is the second level of danger. Its absence is the second level of safety. The paper proposes the way to formalize these ideas and use formal models to construct the states-and-event scale for a given object. The proposed approach can be applied to objects of different nature. The states-and-events scale may be used for transformation of initial objectives state-and-transitions graph to reduce bad classes of states

  4. The critical safety functions and plant operation

    International Nuclear Information System (INIS)

    Corcoran, W.R.; Church, J.F.; Cross, M.T.; Guinn, W.M.; Porter, N.J.

    1981-01-01

    The operator's role in nuclear safety is outlined and the concept of ''safety functions'' introduced. Safety functions are a group of actions that prevent core melt or minimize radiation releases to the general public. They can be used to provide a hierarchy of practical plant protection that an operator should use. The plant safety evaluation uses four inputs in predicting the results of an event: the event initiator, the plant design, the initial plant conditions and setup, and the operator actions. If any of these inputs are not as assumed in the evaluation, confidence that the consequences will be as predicted is reduced. Based on the safety evaluation, the operator has three roles in assuring that the consequences of an event will be no worse than the predicted acceptable results: Maintain plant setup in readiness to properly respond. Operate the plant in a manner such that fewer, milder events minimize the frequency and the severity of adverse events. Monitor the plant to verify that the safety functions are accomplished. The operator needs a systematic approach to mitigating the consequences of an event. The concept of safety functions introduces this systematic approach and presents a hierarchy of protection. If the operator has difficulty identifying an event for any reason, the systematic safety function approach allows accomplishing the overall path of mitigating consequences. Ten functions designed to protect against core melt, preserve containment integrity, prevent indirect release of radioactivity, and maintain vital auxiliaries needed to support the other safety functions are identified

  5. Safety analysis procedures for PHWR

    International Nuclear Information System (INIS)

    Min, Byung Joo; Kim, Hyoung Tae; Yoo, Kun Joong

    2004-03-01

    The methodology of safety analyses for CANDU reactors in Canada, a vendor country, uses a combination of best-estimate physical models and conservative input parameters so as to minimize the uncertainty of the plant behavior predictions. As using the conservative input parameters, the results of the safety analyses are assured the regulatory requirements such as the public dose, the integrity of fuel and fuel channel, the integrity of containment and reactor structures, etc. However, there is not the comprehensive and systematic procedures for safety analyses for CANDU reactors in Korea. In this regard, the development of the safety analyses procedures for CANDU reactors is being conducted not only to establish the safety analyses system, but also to enhance the quality assurance of the safety assessment. In the first phase of this study, the general procedures of the deterministic safety analyses are developed. The general safety procedures are covered the specification of the initial event, selection of the methodology and accident sequences, computer codes, safety analysis procedures, verification of errors and uncertainties, etc. Finally, These general procedures of the safety analyses are applied to the Large Break Loss Of Coolant Accident (LBLOCA) in Final Safety Analysis Report (FSAR) for Wolsong units 2, 3, 4

  6. New Paradigm in Nuclear Safety from Quality Assurance to Safety Management System

    International Nuclear Information System (INIS)

    Lim, Nam-Jin; Park, Chan-Gook; Nam, Ji-Hee; Kim, Kwan-Hyun; Kwon, Hyuk-il; Lee, Young-Gun Lee

    2006-01-01

    The initial concept of Quality Control (QC) controlling the quality of products is now evolving toward the Management System (MS) achieving safety, through Quality Assurance (QA) ensuring the quality of products and Quality Management (QM) managing the quality by a systematic approach. Nuclear safety can be achieved through an integrated MS that ensures the health, environmental, security, quality and economic requirements being considered together with nuclear safety requirements. MS approach is developed through realizing that most of nuclear accidents had occurred not by the malfunction of hardware or equipment, but by the human error. The MS is a set of inter-related or interacting elements (system) that establishes policies and objectives and which enables those objectives to be achieved in an efficient and effective way

  7. Measuring enterprise proactiveness in managing occupational safety

    DEFF Research Database (Denmark)

    Sønderstrup-Andersen, Hans H. K.; Fløcke, Thomas; Mikkelsen, Kim Lyngby

    2010-01-01

    The aim of this paper is to communicate results, and lessons learned, from developing and applying a national questionnaire based survey for measuring the initiation of occupational safety activities in Danish enterprises and public institutions1. The survey is cross-sectional and it is part...... on the safety attitude index....

  8. Safety upgrading of the PAKS Nuclear Plant

    International Nuclear Information System (INIS)

    Vamos, G.; Vigassy, J.

    1993-01-01

    In the last several years the net electricity from the Paks NPP represents almost half of the Hungarian total. The 4 units of Paks belong to the latest generation of the VVER-440 units, the small-sized Russian designed PWRs. Reviewing the main design features of them, the safety merits and safety concerns are summarized. Due to the conservative design and the extensive operating experience the safety merits appear to be more significant than generally believed. The VVER-440 type has two models, the 230 and 213, which have a large number of distinctive safety features. These are highlighted in the section comparisons. A quality assurance program was initiated in Paks very early. A long-term safety upgrading program was also initiated, originating from vendor recommendations, regulatory decisions, in-house operating experience and safety concerns, and independent reviews. The main areas and some examples of the measures are described. This program, like all other activities related to nuclear safety, has been under regulatory control. The specific features of the Hungarian regulatory system are described. For advanced, general and new evaluation of the safety of the units in Paks in accordance with the internationally recommended criteria of the 90's, the project AGNES has been launched with international participation. The scope of this project is summarized. International efforts as the IAEA Regional Project on safety assessment of VVER-440/213 and VVER-440/230 units are underway. Since safety is not only a question of design, but it can be significantly influenced by operations and maintenance practices, the Paks NPP has invited LAEA's OSART and ASSET missions, WANO's Pilot Peer Review

  9. Preliminary Integrated Safety Analysis Status Report

    International Nuclear Information System (INIS)

    Gwyn, D.

    2001-01-01

    This report provides the status of the potential Monitored Geologic Repository (MGR) Integrated Safety Analysis (EA) by identifying the initial work scope scheduled for completion during the ISA development period, the schedules associated with the tasks identified, safety analysis issues encountered, and a summary of accomplishments during the reporting period. This status covers the period from October 1, 2000 through March 30, 2001

  10. Operational safety - the IAEA response

    International Nuclear Information System (INIS)

    Rosen, M.

    1984-01-01

    Nuclear safety is an international issue. The role of the International Atomic Energy Agency is growing because it offers a centre for contact and exchange between East and West, North and South. New initiatives are under way to intensify international co-operative safety efforts through exchange of information on abnormal events at nuclear power plants, and through greater sharing of safety research results. Emergency preparedness also lends itself to international co-operation. A report has been prepared on the need for establishing mutual emergency assistance. By analysing possible constraints to bilateral or multinational efforts in advance, a basis for agreement at the time of an emergency is being worked out. Safety standards have been developed in several areas. The NUSS Codes and Guides, now almost complete, make available to countries starting a nuclear power programme a coherent set of nuclear safety standards. A revised set of Basic Safety Standards for Radiation Protection has been issued in 1982. (author)

  11. The internationalization of nuclear safety

    International Nuclear Information System (INIS)

    Rosen, M.

    1989-01-01

    Nuclear safety is interlinked in many ways with the themes of this conference. In searching for co-operative activities that touch on global energy and environmental problems and on initiatives that relieve international tensions, the ongoing developments in nuclear power safety offer a number of successful examples. Commercial nuclear power has been with us for more than 30 years, and with 26 countries operating plants in addition to 6 more constructing their first, there has been an ongoing global co-operation, coinciding of Chernobyl with Glasnost, along with the increasing awareness of the benefits of common solutions to safety issues, have brought about an internationalization of nuclear safety. Although the main responsibility for safety rests with each operator and its government, a primary driving force expanding international co-operation is the transboundary aspects of nuclear energy, as vividly demonstrated by Chernobyl accident. In this presentation we focus on the mechanisms already in place that foster cooperation in the nuclear safety area

  12. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    other reactor types, including innovative developments in future systems, some of the requirements may not be applicable, or may need some judgment in their interpretation. Various Safety Guides will provide guidance in the interpretation and implementation of these requirements. This publication is intended for use by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies. This publication establishes design requirements for structures, systems and components important to safety that must be met for safe operation of a nuclear power plant, and for preventing or mitigating the consequences of events that could jeopardize safety. It also establishes requirements for a comprehensive safety assessment, which is carried out in order to identify the potential hazards that may arise from the operation of the plant, under the various plant states (operational states and accident conditions). The safety assessment process includes the complementary techniques of deterministic safety analysis and probabilistic safety analysis. These analyses necessitate consideration of postulated initiating events (PlEs), which include many factors that, singly or in combination, may affect safety and which may: originate in the operation of the nuclear power plant itself; be caused by human action; be directly related to the nuclear power plant and its environment. This publication also addresses events that are very unlikely to occur, such as severe accidents that may result in major radioactive releases, and for which it may be appropriate and practicable to provide preventive or mitigatory features in the design. This publication does not address: external natural or human induced events that are extremely unlikely (such as the impact of a meteorite or an artificial satellite); conventional industrial accidents that under no circumstances could affect the safety of the nuclear power plant; or non-radiological effects arising

  13. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    other reactor types, including innovative developments in future systems, some of the requirements may not be applicable, or may need some judgment in their interpretation. Various Safety Guides will provide guidance in the interpretation and implementation of these requirements. This publication is intended for use by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies. This publication establishes design requirements for structures, systems and components important to safety that must be met for safe operation of a nuclear power plant, and for preventing or mitigating the consequences of events that could jeopardize safety. It also establishes requirements for a comprehensive safety assessment, which is carried out in order to identify the potential hazards that may arise from the operation of the plant, under the various plant states (operational states and accident conditions). The safety assessment process includes the complementary techniques of deterministic safety analysis and probabilistic safety analysis. These analyses necessitate consideration of postulated initiating events (PlEs), which include many factors that, singly or in combination, may affect safety and which may: originate in the operation of the nuclear power plant itself. Be caused by human action. Be directly related to the nuclear power plant and its environment. This publication also addresses events that are very unlikely to occur, such as severe accidents that may result in major radioactive releases, and for which it may be appropriate and practicable to provide preventive or mitigatory features in the design. This publication does not address: external natural or human induced events that are extremely unlikely (such as the impact of a meteorite or an artificial satellite). Conventional industrial accidents that under no circumstances could affect the safety of the nuclear power plant. Or non-radiological effects arising

  14. Nuclear Safety. 1997

    International Nuclear Information System (INIS)

    1998-01-01

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  15. Safety of RBMK reactors: Setting the technical framework

    International Nuclear Information System (INIS)

    Lederman, L.

    1996-01-01

    This article reviews major efforts for improving the safety of RBMK reactors through a co-operative IAEA programme initiated in 1992. Specifically covered are technical findings of safety reviews related to the design and operation of the plants, and the documentation of findings through an Agency database intended to facilitate the technical co-ordination of ongoing national and international efforts for improving RBMK safety

  16. Big Data Initiatives for Agroecosystems

    Science.gov (United States)

    NAL has developed a workspace for research groups associated with the i5k initiative, which aims to sequence the genomes of all insesct species known to be important to worldwide agriculture, food safety, medicine, and energy production; all those used as models in biology; the most abundant in worl...

  17. WHO Initiative to Estimate the Global Burden of Foodborne Diseases

    DEFF Research Database (Denmark)

    Havelaar, Arie H.; Cawthorne, Amy; Angulo, Fred

    2013-01-01

    BackgroundThe public health impact of foodborne diseases globally is unknown. The WHO Initiative to Estimate the Global Burden of Foodborne Diseases was launched out of the need to fill this data gap. It is anticipated that this effort will enable policy makers and other stakeholders to set...... appropriate, evidence-informed priorities in the area of food safety. MethodsThe Initiative aims to provide estimates on the global burden of foodborne diseases by age, sex, and region; strengthen country capacity for conducting burden of foodborne disease assessments in parallel with food safety policy...

  18. Probabilistic safety analysis second level of WWER-TOI

    International Nuclear Information System (INIS)

    Chekin, A.A.; Bajkova, E.V.; Levin, V.N.; Shishina, E.S.

    2015-01-01

    Probabilistic safety assessment (PSA) of Level-1 and Level-2 gives a comprehensive qualitative and quantitative evaluation of the safety of the project. The operation of the unit at rated power is considered. As sources of radioactivity in the development of the second-level PSA, nuclear fuel in the core of the reactor is considered. As initiating events, internal initiating events (including de-energizing) are considered, which may arise due to failures of NPP systems, equipment or components, or due to erroneous actions of personnel. In general, an assessment of the level of project safety shows that the WWER-TOI project complies with the requirements of the TOR, as well as all the requirements of modern Russian and foreign regulatory documents in the field of security [ru

  19. Identification and selection of initiating events for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1989-01-01

    This paper describes the current approaches used in probabilistic risk assessment (PRA) to identify and select accident initiating events for study in either probabilistic safety analysis or PRA. Current methods directly apply to fusion facilities as well as other types of industries, such as chemical processing and nuclear fission. These identification and selection methods include the Master Logic Diagram, historical document review, system level Failure Modes and Effects Analysis, and others. A combination of the historical document review, such as Safety Analysis Reports and fusion safety studies, and the Master Logic Diagram with appropriate quality assurance reviews, is suggested for standardizing US fusion PRA effects. A preliminary set of generalized initiating events applicable to fusion facilities derived from safety document review is presented as a framework to start from for the historical document review and Master Logic Diagram approach. Fusion designers should find this list useful for their design reviews. 29 refs., 2 tabs

  20. Identification and selection of initiating events for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1989-01-01

    This paper describes the current approaches used in probabilistic risk assessment (PRA) to identify and select accident initiating events for study in either probabilistic safety analysis or PRA. Current methods directly apply to fusion facilities as well as other types of industries, such as chemical processing and nuclear fission. These identification and selection methods include the Master Logic Diagram, historical document review, system level Failure Modes and Effects Analysis, and others. A combination of the historical document review, such as Safety Analysis Reports and fusion safety studies, and the Master Logic Diagram with appropriate quality assurance reviews, is suggested for standardizing U.S. fusion PRA efforts. A preliminary set of generalized initiating events applicable to fusion facilities derived from safety document review is presented as a framework to start from for the historical document review and Master Logic Diagram approach. Fusion designers should find this list useful for their design reviews. 29 refs., 1 tab

  1. Patient safety--worker safety: building a culture of safety to improve healthcare worker and patient well-being.

    Science.gov (United States)

    Yassi, Annalee; Hancock, Tina

    2005-01-01

    Patient safety within the Canadian healthcare system is currently a high national priority, which merits a comprehensive understanding of the underlying causes of adverse events. Not least among these is worker health and safety, which is linked to patient outcomes. Healthcare workers have a high risk of workplace injuries and more mental health problems than most other occupational groups. Many healthcare professionals feel fatigued, stressed, in pain, or at risk of illness or injury-factors they feel impede their ability to provide consistent quality care. With this background, the Occupational Health and Safety Agency for Healthcare (OHSAH) in British Columbia, jointly governed by healthcare unions and healthcare employers, launched several major initiatives to improve the healthcare workplace. These included the promotion of safe patient handling, adaptive clothing, scheduled toileting, stroke management training, measures to improve management of aggressive behaviour and, of course, infection control-all intended to improve the safety of workers, but also to improve patient safety and quality of care. Other projects also explicitly promoting physical and mental health at work, as well as patient safety are also underway. Results of the projects are at various stages of completion, but ample evidence has already been obtained to indicate that looking after the well-being of healthcare workers results in safer and better quality patient care. While more research is needed, our work to date suggests that a comprehensive systems approach to promoting a climate of safety, which includes taking into account workplace organizational factors and physical and psychological hazards for workers, is the best way to improve the healthcare workplace and thereby patient safety.

  2. Reactor safety: the Nova computer system

    International Nuclear Information System (INIS)

    Eisgruber, H.; Stadelmann, W.

    1991-01-01

    After instances of maloperation, the causes of defects, the effectiveness of the measures taken to control the situation, and possibilities to avoid future recurrences need to be investigated above all before the plant is restarted. The most important aspect in all these efforts is to check the sequence in time, and the completeness, of the control measures initiated automatically. For this verification, a computer system is used instead of time-consuming manual analytical techniques, which produces the necessary information almost in real time. The results are available within minutes after completion of the measures initiated automatically. As all short-term safety functions are initiated by automatic systems, their consistent and comprehensive verification results in a clearly higher level of safety. The report covers the development of the computer system, and its implementation, in the Gundremmingen nuclear power station. Similar plans are being pursued in Biblis and Muelheim-Kaerlich. (orig.) [de

  3. The role of individual diligence in improving safety.

    Science.gov (United States)

    Corbett, Angus; Travaglia, Jo; Braithwaite, Jeffrey

    2011-01-01

    This paper aims to be a theoretical examination of the role of individuals in sponsoring and facilitating effective, systemic change in organisations. Using reports of a number of high-profile initiatives to improve patient safety, it seeks to analyse the role of individual health care professionals in developing and facilitating new systems of care that improve safety and quality. The paper uses recent work in sociology that is concerned with the phenomenon of "sociological citizenship". The authors test whether successful initiators of change in health care can be described as sociological citizens. This notion of sociological citizens is applied to a number of highly successful initiatives to improve safety and quality to extrapolate the factors associated with individual clinician leadership, which may have affected the success of such endeavours. In each of the examples analysed the initiators of change can be characterised as sociological citizens. In reviewing the roles of these charismatic individuals it is evident that they see the relational interdependence between the individuals and organisations and that they use this information to achieve both professional and organisational objectives. The paper uses a case study method to investigate the usefulness of the role of sociological citizenship in interventions that aim to improve patient safety. The paper reviews the key concepts and uses of the concept of sociological citizenship to produce a framework against which the case studies were assessed. The authors suggest that a goal of policy for improving patient safety should be directed to the problem of how hospitals and health care organisations can create the conditions for encouraging the individual diligence and care that is needed to support reliable, safe health care practices. Improving the safety and quality of health care is an important public health initiative. It has also proven to be difficult to achieve sustained reductions in the harm

  4. Master Logic Diagram: An Approach to Identify Initiating Events of HTGRs

    Science.gov (United States)

    Purba, J. H.

    2018-02-01

    Initiating events of a nuclear power plant being evaluated need to be firstly identified prior to applying probabilistic safety assessment on that plant. Various types of master logic diagrams (MLDs) have been proposedforsearching initiating events of the next generation of nuclear power plants, which have limited data and operating experiences. Those MLDs are different in the number of steps or levels and different in the basis for developing them. This study proposed another type of MLD approach to find high temperature gas cooled reactor (HTGR) initiating events. It consists of five functional steps starting from the top event representing the final objective of the safety functions to the basic event representing the goal of the MLD development, which is an initiating event. The application of the proposed approach to search for two HTGR initiating events, i.e. power turbine generator trip and loss of offsite power, is provided. The results confirmed that the proposed MLD is feasiblefor finding HTGR initiating events.

  5. The Occupational Safety and Health Act: Implications for School Administration.

    Science.gov (United States)

    Licht, Kenneth F.

    The Occupational Safety and Health Act (1970) concerns private schools but does not directly affect the operations of public schools or colleges. The intent, however, is to have the States develop and administer their own health and safety programs. Administrators should, therefore, initiate a comprehensive, districtwide safety education and…

  6. Hanford Tanks Initiative quality assurance implementation plan

    International Nuclear Information System (INIS)

    Huston, J.J.

    1998-01-01

    Hanford Tanks Initiative (HTI) Quality Assurance Implementation Plan for Nuclear Facilities defines the controls for the products and activities developed by HTI. Project Hanford Management Contract (PHMC) Quality Assurance Program Description (QAPD)(HNF-PRO599) is the document that defines the quality requirements for Nuclear Facilities. The QAPD provides direction for compliance to 10 CFR 830.120 Nuclear Safety Management, Quality Assurance Requirements. Hanford Tanks Initiative (HTI) is a five-year activity resulting from the technical and financial partnership of the US Department of Energy's Office of Waste Management (EM-30), and Office of Science and Technology Development (EM-50). HTI will develop and demonstrate technologies and processes for characterization and retrieval of single shell tank waste. Activities and products associated with HTI consist of engineering, construction, procurement, closure, retrieval, characterization, and safety and licensing

  7. Using safety crosses for patient self-reflection.

    Science.gov (United States)

    Silverton, Sarah

    The Productive Mental Health Ward programme has been developed to improve efficiency and safety in the NHS. Patients in a medium-secure mental health unit used patient safety crosses as a tool for self-reflection as part of their recovery journey. This article describes how the project was set up as well as initial findings.

  8. Public safety around dams

    Energy Technology Data Exchange (ETDEWEB)

    Bourassa, H. [Centre d' expertise hydrique du Quebec, Quebec, PQ (Canada)

    2009-07-01

    Fourty public dams are managed on a real-time basis by the Centre d'expertise hydrique du Quebec (CEHQ). This presentation described the public dams owned by the CEHQ and discussed the public safety measures at the dams. The dams serve various purposes, including protection against floods; industrial or drinking water supply; resort or recreational activities; hydroelectric development; and wildlife conservation. Trigger events were also discussed, such as the complaint at Rapides-des-Cedres dam and deaths that occurred in 2004 when water from a dam was released without warning. Several photographs were presented to illustrate that people were unaware of the danger. Initiatives aimed at raising awareness and studying public safety issues were discussed. A pilot project was launched and a permanent committee was created to evaluate all aspects of public safety at the dams owned by CEHQ. The first tasks of the committee were to establish requirements for waterway safety barriers, both upstream and downstream, for all public dams; to establish requirements for safety signage for all public dams; and to develop criteria to decide on safety signage at each dam. figs.

  9. Public safety around dams

    Energy Technology Data Exchange (ETDEWEB)

    Bourassa, H [Centre d' expertise hydrique du Quebec, Quebec, PQ (Canada)

    2009-07-01

    Fourty public dams are managed on a real-time basis by the Centre d'expertise hydrique du Quebec (CEHQ). This presentation described the public dams owned by the CEHQ and discussed the public safety measures at the dams. The dams serve various purposes, including protection against floods; industrial or drinking water supply; resort or recreational activities; hydroelectric development; and wildlife conservation. Trigger events were also discussed, such as the complaint at Rapides-des-Cedres dam and deaths that occurred in 2004 when water from a dam was released without warning. Several photographs were presented to illustrate that people were unaware of the danger. Initiatives aimed at raising awareness and studying public safety issues were discussed. A pilot project was launched and a permanent committee was created to evaluate all aspects of public safety at the dams owned by CEHQ. The first tasks of the committee were to establish requirements for waterway safety barriers, both upstream and downstream, for all public dams; to establish requirements for safety signage for all public dams; and to develop criteria to decide on safety signage at each dam. figs.

  10. Regional cooperation on nuclear safety

    International Nuclear Information System (INIS)

    Kato, W.Y.; Chen, J.H.; Kim, D.H.; Simmons, R.B.V.; Surguri, S.

    1985-01-01

    A review has been conducted of a number of multi-national and bilateral arrangements between governments and between utility-sponsored organizations which provide the framework for international cooperation in the field of nuclear safety. These arrangements include the routine exchange operational data, experiences, technical reports and regulatory data, provision of special assistance when requested, collaboration in safety research, and the holding of international conferences and seminars. Areas which may be better suited for cooperation on a regional basis are identified. These areas include: exchange of operational data and experience, sharing of emergency planning information, and collaboration in safety research. Mechanisms to initiate regional cooperation in these areas are suggested

  11. Tutorial on nuclear thermal propulsion safety for Mars

    International Nuclear Information System (INIS)

    Buden, D.

    1992-01-01

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments

  12. Implementing an interprofessional patient safety learning initiative: insights from participants, project leads and steering committee members.

    Science.gov (United States)

    Jeffs, Lianne; Abramovich, Ilona Alex; Hayes, Chris; Smith, Orla; Tregunno, Deborah; Chan, Wai-Hin; Reeves, Scott

    2013-11-01

    Effective teamwork and interprofessional collaboration are vital for healthcare quality and safety; however, challenges persist in creating interprofessional teamwork and resilient professional teams. A study was undertaken to delineate perceptions of individuals involved with the implementation of an interprofessional patient safety competency-based intervention and intervention participants. The study employed a qualitative study design that triangulated data from interviews with six steering committee members and five members of the project team who developed and monitored the intervention and six focus groups with clinical team members who participated in the intervention and implemented local patient safety projects within a large teaching hospital in Canada. Our study findings reveal that healthcare professionals and support staff acquired patient safety competencies in an interprofessional context that can result in improved patient and work flow processes. However, key challenges exist including managing projects amidst competing priorities, lacking physician engagement and sustaining projects. Our findings point to leaders to provide opportunities for healthcare teams to engage in interprofessional teamwork and patient safety projects to improve quality of patient care. Further research efforts should examine the sustainability of interprofessional safety projects and how leaders can more fully engage the participation of all professions, specifically physicians.

  13. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  14. Probabilistic safety analysis procedures guide

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Bari, R.A.; Buslik, A.J.

    1984-01-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of tissues affecting reactor safety. This guide addresses the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant and from loss of offsite electric power. The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage accident sequences, and an explicit treatment and display of uncertainties for the key accident sequences. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance) and the risk associated with external accident initiators, as consensus is developed regarding suitable methodologies in these areas. This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making. Methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study

  15. Mothers' Concerns for Personal Safety and Privacy While Breastfeeding: An Unexplored Phenomenon.

    Science.gov (United States)

    Rosen-Carole, Casey; Allen, Katherine; Fagnano, Maria; Dozier, Ann; Halterman, Jill

    2018-04-01

    Preliminary qualitative research in upstate NY shows new mothers are worried about safety while breastfeeding. Little is known regarding prevalence of these concerns and their effect on breastfeeding outcomes. (1) Determine frequency of breastfeeding safety and privacy concerns; (2) Explore their association with breastfeeding outcomes. Mothers were surveyed immediately and 1-month postpartum about breastfeeding goals; both surveys addressed privacy and safety concerns at home, work, and in public. Outcome data included breastfeeding intent, exclusivity, and duration. Breastfeeding/non-breastfeeding mothers were compared using Chi-square and multivariate analyses. A total of 279 women enrolled. Of these 82.8% initiated breastfeeding; at 1-month 72% provided any breast milk, and 44% were exclusively breastfeeding. About 99% felt safe breastfeeding at home; 25% reported privacy concerns; and 5% felt "vulnerable or unsafe" while breastfeeding. At 1-month, 49% agreed there was a safe place to breastfeed/express milk at work (20% unsure). Non-breastfeeding mothers expressed more safety concerns outside home/at work: 18% breastfeeding versus 28% non-breastfeeding outside home; 27% breastfeeding versus 40% non-breastfeeding at work. Nearly 54% who reported feeling vulnerable/unsafe with breastfeeding initiated breastfeeding, compared with 86% not reporting this concern (p = 0.008). Fewer women initiating breastfeeding reported vulnerability/safety (3% breastfeeding versus 14% non-breastfeeding, p = 0.008) or privacy (22% breastfeeding versus 40% non-breastfeeding, p = 0.19) concerns. Associations held after controlling for age, race, parity, insurance, geography, and marital-status. Significant associations between initiation, privacy, and safety concerns did not extend to duration or exclusivity. Many breastfeeding women reported safety and privacy concerns, especially outside the home and at work, which may influence breastfeeding initiation. Further study

  16. 2011 John M. Eisenberg Patient Safety and Quality Awards. The effect of a novel Housestaff Quality Council on quality and patient safety. Innovation in patient safety and quality at the local level.

    Science.gov (United States)

    Fleischut, Peter M; Faggiani, Susan L; Evans, Adam S; Brenner, Samantha; Liebowitz, Richard S; Forese, Laura; Kerr, Gregory E; Lazar, Eliot J

    2012-07-01

    In 2008 New York-Presbyterian Hospital (NYP)/Weill Cornell Medical Center, New York City, the largest not-for-profit, nonsectarian hospital in the United States, created and implemented a novel approach--the Housestaff Quality Council (HQC)--to engaging house-staff in quality and patient safety activities. The HQC represented an innovative collaboration between the housestaff, the Department of Anesthesiology, the Division of Quality and Patient Safety, the Office of Graduate Medical Education, and senior leadership. As key managers of patient care, the housestaff sought to become involved in the quality and patient safety decision- and policy-making processes at the hospital. Its members were determined to decrease or minimize adverse events by facilitating multimodal communication, ensuring smart work flow, and measuring outcomes to determine best practices. The HQC, which also included frontline hospital staff or managers from areas such as nursing, pharmacy, and information technology, aligned its initiatives with those of the division of quality and patient safety and embarked on two projects--medication reconciliation and use of the electronic medical record. More than three years later, the resulting improvements have been sustained and three new projects--hand hygiene, central line-associated bloodstream infections, and patient handoffs--have been initiated. The HQC model is highly replicable at other teaching institutions as a complementary approach to their other quality and patient safety initiatives. However, the ability to sustain positive momentum is dependent on the ability of residents to invest time and effort in the face of a demanding residency training schedule and focus on specialty-specific clinical and research activities.

  17. The European Nuclear Safety Training and Tutoring Institute

    International Nuclear Information System (INIS)

    2012-01-01

    The European Nuclear Safety Training and Tutoring Institute, ENSTTI, is an initiative of European Technical Safety Organizations (TSO) in order to provide vocational training and tutoring in the methods and practices required to perform assessment in nuclear safety, nuclear security and radiation protection. ENSTTI calls on TSOs' expertise to maximize the transmission of safety and security knowledge, practical experience and culture. Training, tutoring and courses for specialists are achieved through practical lectures, working group and technical visits and lead to a certificate after knowledge testing. ENSTTI contributes to the harmonization of nuclear safety and security practices and to the networking of today and future nuclear safety experts in Europe and beyond. (A.C.)

  18. Hydrogen safety

    International Nuclear Information System (INIS)

    Frazier, W.R.

    1991-01-01

    The NASA experience with hydrogen began in the 1950s when the National Advisory Committee on Aeronautics (NACA) research on rocket fuels was inherited by the newly formed National Aeronautics and Space Administration (NASA). Initial emphasis on the use of hydrogen as a fuel for high-altitude probes, satellites, and aircraft limited the available data on hydrogen hazards to small quantities of hydrogen. NASA began to use hydrogen as the principal liquid propellant for launch vehicles and quickly determined the need for hydrogen safety documentation to support design and operational requirements. The resulting NASA approach to hydrogen safety requires a joint effort by design and safety engineering to address hydrogen hazards and develop procedures for safe operation of equipment and facilities. NASA also determined the need for rigorous training and certification programs for personnel involved with hydrogen use. NASA's current use of hydrogen is mainly for large heavy-lift vehicle propulsion, which necessitates storage of large quantities for fueling space shots and for testing. Future use will involve new applications such as thermal imaging

  19. Blanket safety by GEMSAFE methodology

    International Nuclear Information System (INIS)

    Sawada, Tetsuo; Saito, Masaki

    2001-01-01

    General Methodology of Safety Analysis and Evaluation for Fusion Energy Systems (GEMSAFE) has been applied to a number of fusion system designs, such as R-tokamak, Fusion Experimental Reactor (FER), and the International Thermonuclear Experimental Reactor (ITER) designs in the both stages of Conceptual Design Activities (CDA) and Engineering Design Activities (EDA). Though the major objective of GEMSAFE is to reasonably select design basis events (DBEs) it is also useful to elucidate related safety functions as well as requirements to ensure its safety. In this paper, we apply the methodology to fusion systems with future tritium breeding blankets and make clear which points of the system should be of concern from safety ensuring point of view. In this context, we have obtained five DBEs that are related to the blanket system. We have also clarified the safety functions required to prevent accident propagations initiated by those blanket-specific DBEs. The outline of the methodology is also reviewed. (author)

  20. The National Partnership for Maternal Safety.

    Science.gov (United States)

    DʼAlton, Mary E; Main, Elliott K; Menard, M Kathryn; Levy, Barbara S

    2014-05-01

    Recognition of the need to reduce maternal mortality and morbidity in the United States has led to the creation of the National Partnership for Maternal Safety. This collaborative, broad-based initiative will begin with three priority bundles for the most common preventable causes of maternal death and severe morbidity: obstetric hemorrhage, severe hypertension in pregnancy, and peripartum venous thromboembolism. In addition, three unit-improvement bundles for obstetric services were identified: a structured approach for the recognition of early warning signs and symptoms, structured internal case reviews to identify systems improvement opportunities, and support tools for patients, families, and staff that experience an adverse outcome. This article details the formation of the National Partnership for Maternal Safety and introduces the initial priorities.

  1. Implementation of the INEEL safety analyst training standard

    International Nuclear Information System (INIS)

    Hochhalter, E. E.

    2000-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) safety analysis units at the Idaho National Engineering and Environmental Laboratory (INEEL) are in the process of implementing the recently issued INEEL Safety Analyst Training Standard (STD-1107). Safety analyst training and qualifications are integral to the development and maintenance of core safety analysis capabilities. The INEEL Safety Analyst Training Standard (STD-1107) was developed directly from EFCOG Training Subgroup draft safety analyst training plan template, but has been adapted to the needs and requirements of the INEEL safety analysis community. The implementation of this Safety Analyst Training Standard is part of the Integrated Safety Management System (ISMS) Phase II Implementation currently underway at the INEEL. The objective of this paper is to discuss (1) the INEEL Safety Analyst Training Standard, (2) the development of the safety analyst individual training plans, (3) the implementation issues encountered during this initial phase of implementation, (4) the solutions developed, and (5) the implementation activities remaining to be completed

  2. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  3. Safety distance for preventing hot particle ignition of building insulation materials

    Directory of Open Access Journals (Sweden)

    Jiayun Song

    2014-01-01

    Full Text Available Trajectories of flying hot particles were predicted in this work, and the temperatures during the movement were also calculated. Once the particle temperature decreased to the critical temperature for a hot particle to ignite building insulation materials, which was predicted by hot-spot ignition theory, the distance particle traveled was determined as the minimum safety distance for preventing the ignition of building insulation materials by hot particles. The results showed that for sphere aluminum particles with the same initial velocities and diameters, the horizontal and vertical distances traveled by particles with higher initial temperatures were higher. Smaller particles traveled farther when other conditions were the same. The critical temperature for an aluminum particle to ignite rigid polyurethane foam increased rapidly with the decrease of particle diameter. The horizontal and vertical safety distances were closely related to the initial temperature, diameter and initial velocity of particles. These results could help update the safety provision of firework display.

  4. A multi-tiered approach to safety education.

    Science.gov (United States)

    Oates, Kim; Sammut, John; Kennedy, Peter

    2013-08-01

    The World Health Organization has recognised that patient safety education should begin at the undergraduate level. This should not just be for medical students, but for all students in the health professions. Although all students in the health professions should receive a basic grounding in patient safety, there is also a need to develop future leaders in this field. As a result of widespread early student exposure, some students may become interested in learning more. It follows that a postgraduate approach is also needed. The New South Wales Clinical Excellence Commission (CEC) has initiated a tiered approach to patient safety education by providing patient safety teaching in medical, nursing and allied health schools. Teaching is provided in cooperation with the host university, and is interactive, using a mixture of interactive lectures, video clips, films and break-out groups to discuss scenarios and feedback from students to their peers about the concepts they have discussed. For medical graduates, the CEC has initiated patient safety teaching in the early postgraduate years, and provides an elective in patient safety for trainee doctor specialists as part of their accredited training. This process helps to identify and mentor future medical leaders in this field. In addition to teaching the core principles of patient safety to a wide range of students in the health professions, an approach for developing future leaders will provide additional opportunities for motivated students and create opportunities for continuing development in the early postgraduate years and beyond. © 2013 John Wiley & Sons Ltd.

  5. Panel 1: Safety design criteria

    International Nuclear Information System (INIS)

    Yllera, Javier

    2013-01-01

    There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors

  6. The ‘Medication Safety Minute’− Microlearning in Medicine

    LENUS (Irish Health Repository)

    Relihan, Eileen

    2018-04-06

    Summary of an initiative of St. James’s Hospital (SJH) medication safety programme to highlighting prescribing safety issues. The project the ‘Medication Safety Minute\\' was based on the concept of ‘bite-sized learning’. The aim was to deliver a message which could be which could be read and understood in one minute or less. The project was selected for the HSE excellence awards showcase.

  7. Software Quality Assurance for Nuclear Safety Systems

    International Nuclear Information System (INIS)

    Sparkman, D R; Lagdon, R

    2004-01-01

    The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: (sm b ullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (sm b ullet) Considers the larger system that uses the software and its impacts (sm b ullet) Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

  8. Fuel safety research 1999

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-07-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

  9. DIVERSIFICATION OF A SAFETY FOOTWEAR PRODUCT

    OpenAIRE

    HARNAGEA Marta Cătălina; SECAN Cristina

    2017-01-01

    Product diversification is a usual strategy of footwear producers. As a requirement related to competitiveness in this domain, diversification can be done by practical application of some criteria. Considering this aspect, the paper proposes a research on the diversification in the case of a safety footwear product by modifying its component patterns, while keeping the initial shape of the product. Thus, starting from a safety shoe model, diversification was performed by changing the configur...

  10. Initiating events frequency determination

    International Nuclear Information System (INIS)

    Simic, Z.; Mikulicic, V.; Vukovic, I.

    2004-01-01

    The paper describes work performed for the Nuclear Power Station (NPS). Work is related to the periodic initiating events frequency update for the Probabilistic Safety Assessment (PSA). Data for all relevant NPS initiating events (IE) were reviewed. The main focus was on events occurring during most recent operating history (i.e., last four years). The final IE frequencies were estimated by incorporating both NPS experience and nuclear industry experience. Each event was categorized according to NPS individual plant examination (IPE) initiating events grouping approach. For the majority of the IE groups, few, or no events have occurred at the NPS. For those IE groups with few or no NPS events, the final estimate was made by means of a Bayesian update with general nuclear industry values. Exceptions are rare loss-of-coolant-accidents (LOCA) events, where evaluation of engineering aspects is used in order to determine frequency.(author)

  11. Westinghouse Hanford Company safety analysis reports and technical safety requirements upgrade program

    International Nuclear Information System (INIS)

    Busche, D.M.

    1995-09-01

    During Fiscal Year 1992, the US Department of Energy, Richland Operations Office (RL) separately transmitted the following US Department of Energy (DOE) Orders to Westinghouse Hanford Company (WHC) for compliance: DOE 5480.21, ''Unreviewed Safety Questions,'' DOE 5480.22, ''Technical Safety Requirements,'' and DOE 5480.23, ''Nuclear Safety Analysis Reports.'' WHC has proceeded with its impact assessment and implementation process for the Orders. The Orders are closely-related and contain some requirements that are either identical, similar, or logically-related. Consequently, WHC has developed a strategy calling for an integrated implementation of the three Orders. The strategy is comprised of three primary objectives, namely: Obtain DOE approval of a single list of DOE-owned and WHC-managed Nuclear Facilities, Establish and/or upgrade the ''Safety Basis'' for each Nuclear Facility, and Establish a functional Unreviewed Safety Question (USQ) process to govern the management and preservation of the Safety Basis for each Nuclear Facility. WHC has developed policy-revision and facility-specific implementation plans to accomplish near-term tasks associated with the above strategic objectives. This plan, which as originally submitted in August 1993 and approved, provided an interpretation of the new DOE Nuclear Facility definition and an initial list of WHC-managed Nuclear Facilities. For each current existing Nuclear Facility, existing Safety Basis documents are identified and the plan/status is provided for the ISB. Plans for upgrading SARs and developing TSRs will be provided after issuance of the corresponding Rules

  12. Improving teamwork, trust and safety: an ethnographic study of an interprofessional initiative.

    Science.gov (United States)

    Jones, Aled; Jones, Delyth

    2011-05-01

    This study explored the perceptions of staff in an interprofessional team based on a medical rehabilitation ward for older people, following the introduction of a service improvement programme designed to promote better teamworking. The study aimed to address a lack of in-depth qualitative research that could explain the day-to-day realities of interprofessional teamworking in healthcare. All members of the team participated, (e.g. nurses, doctors, physiotherapists, social worker, occupational therapists), and findings suggest that interprofessional teamworking improved over the 12-month period. Four themes emerged from the data offering insights into the development and effects of better interprofessional teamworking: the emergence of collegial trust within the team, the importance of team meetings and participative safety, the role of shared objectives in conflict management and the value of autonomy within the team. Reductions in staff sickness/absence levels and catastrophic/major patient safety incidents were also detected following the introduction of the service improvement programme.

  13. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    increasing recognition. The event was rounded off by a poster exhibition. Technical plenary presentations comprised: - Welcome by the Directors of AVN, GRS and IRSN; - Safety Improvements - objectives and methods (Pieter De Gelder, Martial Jorel, Heinz Liemersdorf); - NPP safety improvements - licensees' motivation and concerns (Ingvar Berglund); - Implementation of safety improvements - the role of the authority (Ivan Lux). Five seminars followed addressing the items: - Seminar 1, Nuclear Installation Safety - Assessment and Analysis; - Seminar 2, Nuclear Installation Safety - Research; - Seminar 3, Environment and Radiation Protection; - Seminar 4, Nuclear Material and Nuclear Facilities Security; - Seminar 5, Waste Management. A poster and computer demonstrations were available for consultations throughout the Forum. The poster presented the consequences of the Chernobyl accident and REDAC, the radioecological database of the French-German initiative.

  14. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    increasing recognition. The event was rounded off by a poster exhibition. Technical plenary presentations comprised: - Welcome by the Directors of AVN, GRS and IRSN; - Safety Improvements - objectives and methods (Pieter De Gelder, Martial Jorel, Heinz Liemersdorf); - NPP safety improvements - licensees' motivation and concerns (Ingvar Berglund); - Implementation of safety improvements - the role of the authority (Ivan Lux). Five seminars followed addressing the items: - Seminar 1, Nuclear Installation Safety - Assessment and Analysis; - Seminar 2, Nuclear Installation Safety - Research; - Seminar 3, Environment and Radiation Protection; - Seminar 4, Nuclear Material and Nuclear Facilities Security; - Seminar 5, Waste Management. A poster and computer demonstrations were available for consultations throughout the Forum. The poster presented the consequences of the Chernobyl accident and REDAC, the radioecological database of the French-German initiative.

  15. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Cadwallader; J. S. Herring

    1999-09-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  16. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  17. The safety issues of medical robotics

    Energy Technology Data Exchange (ETDEWEB)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-08-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory.

  18. The safety issues of medical robotics

    International Nuclear Information System (INIS)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-01-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory

  19. Balancing safety and economics

    International Nuclear Information System (INIS)

    Kroeger, W.; Fischer, P.U.

    2000-01-01

    The safety requirements of NPPs have always aimed at limiting societal risks. This risk approach initially resulted in deterministic design criteria and concepts. In the 1980s the paradigm 'safety at all costs' arose and often led to questionable backfitting measures. Conflicts between new requirements, classical design concepts and operational demands were often ignored. The design requirements for advanced reactors ensure enhanced protection against severe accidents. Still, it is questionable whether the 'no-damage-outside-the-fence' criteria can be achieved deterministically and at competitive costs. Market deregulation and utility privatisation call for a balance between safety and costs, without jeopardising basic safety concepts. An ideal approach must be risk-based and imply modern PSAs and new methods for cost-benefit and ALARA analyses, embed nuclear risks in a wider risk spectrum, but also make benefits transparent within the context of a broader life experience. Governments should define basic requirements, minimum standards and consistent comparison criteria, and strengthen operator responsibility. Internationally sufficient and binding safety requirements must be established and nuclear technology transfer handled in a responsible way, while existing plants, with their continuous backfitting investments, should receive particular attention. (orig.)

  20. Efficacy and safety of a pharmacist-managed inpatient anticoagulation service for warfarin initiation and titration.

    Science.gov (United States)

    Wong, Y M; Quek, Y-N; Tay, J C; Chadachan, V; Lee, H K

    2011-10-01

    Anticoagulation consultations provided by a pharmacist-staffed inpatient service, similar to the experience reported in outpatient anticoagulation clinics, can potentially improve anticoagulation control and outcomes. At Tan Tock Seng Hospital, a 1200-bed acute care teaching hospital in Singapore, pharmacist-managed anticoagulation clinics have been in place since 1997. Pharmacist-managed services were extended to inpatient consultations in anticoagulation management from April 2006. Our objective was to assess the effect of implementing a pharmacist-managed inpatient anticoagulation service. This was a single-centre cohort study. Baseline data from 1 January 2006 to 31 March 2006 were collected and compared with post-implementation data from 1 April 2006 to 31 March 2007. Patients newly started on warfarin for deep vein thrombosis, pulmonary embolism or atrial fibrillation in general medicine and surgery departments were included. The three endpoints were as follows: (i) percentage of international normalized ratios (INRs) achieving therapeutic range within 5 days, (ii) INRs more than 4 during titration and (iii) subtherapeutic INRs on discharge. A total of 26 patients in the control period were compared with 144 patients who had received dosing consultations by a pharmacist during the initiation of warfarin. The provision of pharmacist consult resulted in 88% compared to 38% (P < 0·001) of INR values achieving therapeutic range within 5 days. There was a reduction in INR values of more than 4 during titration from 27% to 2% (P < 0·001), and subtherapeutic INR values on discharge without low molecular weight heparin from 15% to 0% (P < 0·001). The mean time to therapeutic INR was reduced from 6·5 to 3·9 days (P < 0·001) and mean length of stay after initiation of warfarin from 11 to 7·7 days (P = 0·004). Inpatient anticoagulation care and outcomes were significantly improved by a pharmacist-managed anticoagulation service. The time to therapeutic INR was

  1. Knowledge Representation in Patient Safety Reporting: An Ontological Approach

    Directory of Open Access Journals (Sweden)

    Liang Chen

    2016-10-01

    Full Text Available Purpose: The current development of patient safety reporting systems is criticized for loss of information and low data quality due to the lack of a uniformed domain knowledge base and text processing functionality. To improve patient safety reporting, the present paper suggests an ontological representation of patient safety knowledge. Design/methodology/approach: We propose a framework for constructing an ontological knowledge base of patient safety. The present paper describes our design, implementation, and evaluation of the ontology at its initial stage. Findings: We describe the design and initial outcomes of the ontology implementation. The evaluation results demonstrate the clinical validity of the ontology by a self-developed survey measurement. Research limitations: The proposed ontology was developed and evaluated using a small number of information sources. Presently, US data are used, but they are not essential for the ultimate structure of the ontology. Practical implications: The goal of improving patient safety can be aided through investigating patient safety reports and providing actionable knowledge to clinical practitioners. As such, constructing a domain specific ontology for patient safety reports serves as a cornerstone in information collection and text mining methods. Originality/value: The use of ontologies provides abstracted representation of semantic information and enables a wealth of applications in a reporting system. Therefore, constructing such a knowledge base is recognized as a high priority in health care.

  2. Global process industry initiatives to reduce major accident hazards

    Energy Technology Data Exchange (ETDEWEB)

    Pitblado, Robin [DNV Energy Houston, TX (United States). SHE Risk Management; Pontes, Jose [DNV Energy Rio de Janeiro, RJ (Brazil). Americas Region; Oliveira, Luiz [DNV Energy Rio de Janeiro, RJ (Brazil)

    2008-07-01

    Since 2000, disasters at Texas City, Toulouse, Antwerp, Buncefield, P-36 and several near total loss events offshore in Norway have highlighted that major accident process safety is still a serious issue. Hopes that Process Safety Management or Safety Case regulations would solve these issues have not proven true. The Baker Panel recommended to BP several actions mainly around leadership, incentives, metrics, safety culture and more effective implementation of PSM systems. In Europe, an approach built around mechanical integrity and safety barriers, especially relating to technical safety systems, is being widely adopted. DNV has carried out a global survey of process industry initiatives, by interview and by literature review, for both upstream and downstream activities, to identify what the industry itself is planning to implement to enhance process safety in the next 5 - 10 years. This shows that an approach combining Baker Panel and EU barrier approaches and some nuclear industry real-time risk management approaches might be the best means to achieve a factor of 3-4 improvement in process safety. (author)

  3. Communicating on risk and safety in terms of awareness

    International Nuclear Information System (INIS)

    Hammar, L.; Andersson, Kjell

    1999-01-01

    'Safety awareness' is proposed as a possibly constructive concept for the purpose of promoting initiatives in nuclear safety work and gaining improved understanding when communicating on nuclear safety. Safety is thus conceived as resulting essentially from and actually constituting awareness of critical factors in regard of safety. The concept aims specifically at promoting the view of 'safety' as 'awareness of required conditions for being in control of risk'. It aims as well at making clearer sense in calling for constant improvement of safety, according to practice in a safety culture. This proposed view would be expected to lead to applying the usual types of safety criteria but offers the merit of attracting due attention to 'awareness goals' in process oriented safety management which are fundamental to maintaining and improving safety. Applications are discussed in regard of communicating on nuclear safety between decision-makers and the general public, developing and maintaining safety culture, integrating specialist expert contributions in over-all safety assessment, setting safety goals and using safety indicators

  4. Safety analysis and environmental effects of fusion concepts

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Fusion reactor concepts have been analyzed to determine the probable interactions with the environment and the resultant environmental effects. Two research projects on tritium oxidation in the atmosphere and carbon-14 formation in fusion reactors are briefly described. A study and report were completed, investigating the potential public safety impact of accidents in fusion power plants. After reviewing the existing information on conceptual fusion reactor designs, PNL identified areas of safety concern, making recommendations on how development of safety information might be best accomplished. Inventories of potentially dispersible toxic materials were classified, and general conclusions were made about their relative importance. The report specifies energy sources with a potential to initiate or propagate an accident. An important product of the study was an assessment logic developed to identify potential accident scenarios that could lead to the release of contaminants to the environment. Though the limited amount of fusion design information allows only a general assessment of accident-initiating events, the logic provides a method for making more detailed safety analyses as more design information becomes available. The same logic was used to identify technological areas where an R and D investment would enhance the technical bases for fusion designs as well as the understanding of safety implications in fusion systems

  5. Influence of initial conditions on rod behaviour during boiling crisis phase following a reactivity initiated accident

    International Nuclear Information System (INIS)

    Georgenthum, V.; Sugiyama, T.

    2010-01-01

    In the frame of their research programs on high burn-up fuel safety, the French Institute for Radioprotection and Nuclear Safety (IRSN) and the Japan Atomic Energy Agency (JAEA) performed a large set of tests devoted to the study of PWR fuel rod behavior during Reactivity Initiated Accident (RIA) respectively in the CABRI reactor and in the NSRR reactor. The reactor test conditions are different in terms of coolant nature, temperature and pressure. In the CABRI reactor, tests were performed until now with sodium coolant at 280 Celsius degrees and 3 bar. In the NSRR reactor most of the tests were performed with stagnant water at 20 C. degrees and atmospheric pressure but recently a new high temperature high pressure capsule has been developed which allows to performed tests at up to 280 Celsius degrees and 70 bar. The paper discusses the influence of test conditions on rod behaviour during boiling phase, based on tests results and SCANAIR code calculations. The study shows that when the boiling crisis is reached, the initial inner and outer rod pressure have an essential impact on the clad straining and possible ballooning. The analysis of the different test conditions makes it possible to discriminate the influence of initial conditions on the different phases of the transient and is useful for modelling and code development. (authors)

  6. Report of Committee for JAEA Internationalization Initiative (Translated document)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    In global circumstances surrounding nuclear energy, the role expected by the Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has promoted an initiative for an international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA has established the 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve the current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  7. Report of Committee for JAEA Internationalization Initiative (Translated document)

    International Nuclear Information System (INIS)

    2013-07-01

    In global circumstances surrounding nuclear energy, the role expected by the Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has promoted an initiative for an international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA has established the 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve the current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  8. Initiation Temperature for Runaway Tri-n-Butyl Phosphate/Nitric Acid Reaction

    Energy Technology Data Exchange (ETDEWEB)

    Rudisill, T.S.

    2000-11-28

    During a review of the H-Canyon authorization basis, Defense Nuclear Facility Safety Board (DNFSB) staff members questioned the margin of safety associated with a postulated tri-n-butyl phosphate (TBP)/nitric acid runaway reaction due to the inadvertent heating of a canyon tank containing greater than 3000 lbs (1362 kg) of TBP. The margin of safety was partially based on experiments and calculations performed by the Actinide Technology Section (ATS) to support deletion of indication of tank agitation as a Safety Class System. In the technical basis for deletion of this system, ATS personnel conservatively calculated the equilibrium temperature distribution of a canyon tank containing TBP and nitric acid layers which were inadvertently heated by a steam jet left on following a transfer. The maximum calculated temperature (128 degrees C) was compared to the minimum initiation temperature for a runaway reaction (greater than 130 degrees C) documented by experimental work in the mid 195 0s. In this work, the initiation temperature as a function of nitric acid concentration was measured for 0 and 20 wt percent dissolved solids. The DNFSB staff members were concerned that data for 0 wt percent dissolved solids were not conservative given the facts that data for 20 wt percent dissolved solids show initiation temperatures at or below 130 degrees C and H-Canyon solutions normally contained a small amount of dissolved solids.

  9. Preliminary fire hazards analysis for W-211, Initial Tank Retrieval Systems

    International Nuclear Information System (INIS)

    Huckfeldt, R.A.

    1995-01-01

    A fire hazards analysis (FHA) was performed for Project W-211, Initial Tank Retrieval System (ITRS), at the Department of Energy (DOE) Hanford site. The objectives of this FHA was to determine (1) the fire hazards that expose the Initial Tank Retrieval System or are inherent in the process, (2) the adequacy of the fire-safety features planned, and (3) the degree of compliance of the project with specific fire safety provisions in DOE orders and related engineering codes and standards. The scope included the construction, the process hazards, building fire protection, and site wide fire protection. The results are presented in terms of the fire hazards present, the potential extent of fire damage, and the impact on employees and public safety. This study evaluated the ITRS with respect to its use at Tank 241-SY-101 only

  10. Establishment of Management System for Korea Institute of Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Han, Soon-Kyoo; Ha, Jong-Tae; Chung, Ku-Young; Lee, Je-Hang; Kim, Kyung-Im [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In order to optimize of nuclear safety regulation in the rapidly changing nuclear safety environment, Korea government determined that the existing safety standards needed to be reviewed from Integrated Regulatory Review Service(IRRS) team of International Atomic Energy Agency(IAEA). For optimizations of nuclear safety regulation, the reviews were performed by IAEA IRRS team from July 10-22, 2011. In the results of 2011 IRRS mission, 12 suggestion and 10 recommendation were found. To confirm follow-up measures, IRRS follow-up mission would be also performed by IRRS team 18-24 months later after the mission was over. In order to prepare the IRRS follow-up mission, the establishment of MS of Korea Institute of Nuclear Safety(KINS) had been initiated by reflecting the 4 found supplement items in module 4 and IAEA GS-R-3 requirements. As a result of the initiation, MS of KINS was established. To introduce the MS of KINS and gather another suggestions for its enhancement, the MS was considered as a theme.

  11. Safety climate in Swiss hospital units: Swiss version of the Safety Climate Survey

    Science.gov (United States)

    Gehring, Katrin; Mascherek, Anna C.; Bezzola, Paula

    2015-01-01

    Abstract Rationale, aims and objectives Safety climate measurements are a broadly used element of improvement initiatives. In order to provide a sound and easy‐to‐administer instrument for the use in Swiss hospitals, we translated the Safety Climate Survey into German and French. Methods After translating the Safety Climate Survey into French and German, a cross‐sectional survey study was conducted with health care professionals (HCPs) in operating room (OR) teams and on OR‐related wards in 10 Swiss hospitals. Validity of the instrument was examined by means of Cronbach's alpha and missing rates of the single items. Item‐descriptive statistics group differences and percentage of ‘problematic responses’ (PPR) were calculated. Results 3153 HCPs completed the survey (response rate: 63.4%). 1308 individuals were excluded from the analyses because of a profession other than doctor or nurse or invalid answers (n = 1845; nurses = 1321, doctors = 523). Internal consistency of the translated Safety Climate Survey was good (Cronbach's alpha G erman = 0.86; Cronbach's alpha F rench = 0.84). Missing rates at item level were rather low (0.23–4.3%). We found significant group differences in safety climate values regarding profession, managerial function, work area and time spent in direct patient care. At item level, 14 out of 21 items showed a PPR higher than 10%. Conclusions Results indicate that the French and German translations of the Safety Climate Survey might be a useful measurement instrument for safety climate in Swiss hospital units. Analyses at item level allow for differentiating facets of safety climate into more positive and critical safety climate aspects. PMID:25656302

  12. Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

    International Nuclear Information System (INIS)

    2015-12-01

    Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

  13. A nuclear safety in 21 century

    International Nuclear Information System (INIS)

    Osmachkin, V.S.

    2003-01-01

    In the paper some topics of nuclear safety are discussed, namely current situation in the world energetics and a potential of nuclear energy for sustainable development of the world, Nuclear Safety Standards and modern trends in Safety Regulation, Radiation Protection Standards are rather conservative, are based on disputable approaches and have to be more pragmatic, necessity to overcome the syndromes of awful consequences of nuclear accidents at nuclear plants, residual risks of nuclear accidents have to be covered by clear compulsory insurance actions. It is shown, that now it is worthwhile to consider efficiency of existing methods of nuclear safety regulation. It is possible, that an idea of guaranteed safety [1] could become a new approach to nuclear safety. It is based on practically total elimination of severe accidents and insurance of residual risks of nuclear accidents. The realization of such idea necessitates the consideration of all spectrum of initiating events, human errors and man-made actions, more realistically predicting consequences of accidents and the probable economical detriments. It will be a benefit for gaining public support to nuclear power. (author)

  14. Health and Safety Management Plan for the Plutonium Stabilization and Packaging System

    International Nuclear Information System (INIS)

    1996-01-01

    This Health and Safety Management Plan (HSMP) presents safety and health policies and a project health and safety organizational structure designed to minimize potential risks of harm to personnel performing activities associated with Plutonium Stabilization and Packaging System (Pu SPS). The objectives of the Pu SPS are to design, fabricate, install, and startup of a glovebox system for the safe repackaging of plutonium oxides and metals, with a requirement of a 50-year storage period. This HSMP is intended as an initial project health and safety submittal as part of a three phase effort to address health and safety issues related to personnel working the Pu SPS project. Phase 1 includes this HSMP and sets up the basic approach to health and safety on the project and addresses health and safety issues related to the engineering and design effort. Phase 2 will include the Site Specific Construction health and Safety Plan (SSCHSP). Phase 3 will include an additional addendum to this HSMP and address health and safety issues associated with the start up and on-site test phase of the project. This initial submittal of the HSMP is intended to address those activities anticipated to be performed during phase 1 of the project. This HSMP is intended to be a living document which shall be modified as information regarding the individual tasks associated with the project becomes available. These modifications will be in the form of addenda to be submitted prior to the initiation of each phase of the project. For additional work authorized under this project this HSMP will be modified as described in section 1.4

  15. Fusion safety program Annual report, Fiscal year 1995

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

  16. Improving patient safety through quality assurance.

    Science.gov (United States)

    Raab, Stephen S

    2006-05-01

    Anatomic pathology laboratories use several quality assurance tools to detect errors and to improve patient safety. To review some of the anatomic pathology laboratory patient safety quality assurance practices. Different standards and measures in anatomic pathology quality assurance and patient safety were reviewed. Frequency of anatomic pathology laboratory error, variability in the use of specific quality assurance practices, and use of data for error reduction initiatives. Anatomic pathology error frequencies vary according to the detection method used. Based on secondary review, a College of American Pathologists Q-Probes study showed that the mean laboratory error frequency was 6.7%. A College of American Pathologists Q-Tracks study measuring frozen section discrepancy found that laboratories improved the longer they monitored and shared data. There is a lack of standardization across laboratories even for governmentally mandated quality assurance practices, such as cytologic-histologic correlation. The National Institutes of Health funded a consortium of laboratories to benchmark laboratory error frequencies, perform root cause analysis, and design error reduction initiatives, using quality assurance data. Based on the cytologic-histologic correlation process, these laboratories found an aggregate nongynecologic error frequency of 10.8%. Based on gynecologic error data, the laboratory at my institution used Toyota production system processes to lower gynecologic error frequencies and to improve Papanicolaou test metrics. Laboratory quality assurance practices have been used to track error rates, and laboratories are starting to use these data for error reduction initiatives.

  17. Gas-cooled fast reactor safety

    International Nuclear Information System (INIS)

    Rickard, C.L.; Simon, R.H.; Buttemer, D.R.

    1977-01-01

    Initial conceptual design work on the GCFR began in the USA in the early 1960s and since the later 1960s has proceeded with considerable international cooperation. A 300 MWe GCFR demonstration plant employing three main cooling loops is currently being developed at General Atomic. A major preapplication licensing review of this demonstration plant was initiated in 1971 leading in 1974 to publication of a Safety Evaluation Report by the USAEC Directorate of Licensing. The preapplication review is continuing by addressing areas of concern identified in this report such that a major part of the work necessary to support the actual licensing of a GCFR demonstration plant has been established. The safety performance of the GCFR demonstration plant is based upon its inherent safety characteristics among which are the single phase and chemically inert coolant which is not activated and has a low reactivity worth, the negative core power and temperature reactivity coefficients and the small and negative steam reactivity worth. Recent studies of larger core designs indicate that as the reactor size increases central fuel, clad and coolant reactivity worths decrease and the Doppler coefficient becomes more negative. These inherent safety characteristics are complemented by safety design features such as enclosing the entire primary coolant system within a prestressed concrete pressure vessel (PCRV), providing two independent and diverse shutdown systems and residual heat removal (RHR) systems, limiting the worth of control rods to less than $1, employing pressure-equalized fuel rods, a core supported rigidly at its upper end and otherwise unrestrained and coolant downflow within the core to enhance debris removal should local melting occur. The structurally redundant PCRV design allows the potential depressurization leak area to be controlled and, since the PCRV is located within a containment building, coolant is present even after a depressurization accident and each RHR

  18. Green light for the methodology file. Periodical safety review 2016 has begun

    International Nuclear Information System (INIS)

    2014-01-01

    Every ten years, the organisational framework and the facilities of the Belgian Nuclear Research Center SCK-CEN are subject to an encompassing safety evaluation. Together with initiatives arising from the stress tests, a large number of safety studies and actions are scheduled until 2018. The article discusses the ongoing safety review.

  19. A review for identification of initiating events in event tree development process on nuclear power plants

    International Nuclear Information System (INIS)

    Riyadi, Eko H.

    2014-01-01

    Initiating event is defined as any event either internal or external to the nuclear power plants (NPPs) that perturbs the steady state operation of the plant, if operating, thereby initiating an abnormal event such as transient or loss of coolant accident (LOCA) within the NPPs. These initiating events trigger sequences of events that challenge plant control and safety systems whose failure could potentially lead to core damage or large early release. Selection for initiating events consists of two steps i.e. first step, definition of possible events, such as by evaluating a comprehensive engineering, and by constructing a top level logic model. Then the second step, grouping of identified initiating event's by the safety function to be performed or combinations of systems responses. Therefore, the purpose of this paper is to discuss initiating events identification in event tree development process and to reviews other probabilistic safety assessments (PSA). The identification of initiating events also involves the past operating experience, review of other PSA, failure mode and effect analysis (FMEA), feedback from system modeling, and master logic diagram (special type of fault tree). By using the method of study for the condition of the traditional US PSA categorization in detail, could be obtained the important initiating events that are categorized into LOCA, transients and external events

  20. Passive safety systems for integral reactors

    International Nuclear Information System (INIS)

    Kuul, V.S.; Samoilov, O.B.

    1996-01-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs

  1. Passive safety systems for integral reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuul, V S; Samoilov, O B [OKB Mechanical Engineering (Russian Federation)

    1996-12-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs.

  2. Patient safety trilogy: perspectives from clinical engineering.

    Science.gov (United States)

    Gieras, Izabella; Sherman, Paul; Minsent, Dennis

    2013-01-01

    This article examines the role a clinical engineering or healthcare technology management (HTM) department can play in promoting patient safety from three different perspectives: a community hospital, a national government health system, and an academic medical center. After a general overview, Izabella Gieras from Huntington Hospital in Pasadena, CA, leads off by examining the growing role of human factors in healthcare technology, and describing how her facility uses clinical simulations in medical equipment evaluations. A section by Paul Sherman follows, examining patient safety initiatives from the perspective of the Veterans Health Administration with a focus on hazard alerts and recalls. Dennis Minsent from Oregon Health & Science University writes about patient safety from an academic healthcare perspective, and details how clinical engineers can engage in multidisciplinary safety opportunities.

  3. Identification of Initiating Events for PGSFR

    International Nuclear Information System (INIS)

    Kim, Jintae; Jae, Moosung

    2016-01-01

    The Sodium-cooled Fast Reactor (SFR) is by far the most advanced reactor of the six Generation IV reactors. The SFR uses liquid sodium as the reactor coolant, which has superior heat transport characteristics. It also allows high power density with low coolant volume fraction and operation at low pressure. In Korea, KAERI has been developing Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR) that employs passive safety systems and inherent reactivity feedback effects. In order to prepare for the licensing, it is necessary to assess the safety of the reactor. Thus, the objective of this study is to conduct accident sequence analysis that can contribute to risk assessment. The analysis embraces identification of initiating events and accident sequences development. PGSFR is to test and demonstrate the performance of transuranic (TRU)-containing metal fuel required for a commercial SFR, and to demonstrate the TRU transmutation capability of a burner reactor as a part of an advanced fuel cycle system. Initiating events that can happen in PGSFR were identified through the MLD method. This method presents a model of a plant in terms of individual events and their combinations in a systematic and logical way. The 11 identified initiating events in this study include the events considered in the past analysis that was conducted for PRISM-150

  4. Identification of Initiating Events for PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jintae; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2016-10-15

    The Sodium-cooled Fast Reactor (SFR) is by far the most advanced reactor of the six Generation IV reactors. The SFR uses liquid sodium as the reactor coolant, which has superior heat transport characteristics. It also allows high power density with low coolant volume fraction and operation at low pressure. In Korea, KAERI has been developing Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR) that employs passive safety systems and inherent reactivity feedback effects. In order to prepare for the licensing, it is necessary to assess the safety of the reactor. Thus, the objective of this study is to conduct accident sequence analysis that can contribute to risk assessment. The analysis embraces identification of initiating events and accident sequences development. PGSFR is to test and demonstrate the performance of transuranic (TRU)-containing metal fuel required for a commercial SFR, and to demonstrate the TRU transmutation capability of a burner reactor as a part of an advanced fuel cycle system. Initiating events that can happen in PGSFR were identified through the MLD method. This method presents a model of a plant in terms of individual events and their combinations in a systematic and logical way. The 11 identified initiating events in this study include the events considered in the past analysis that was conducted for PRISM-150.

  5. Requirements of safety and reliability

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1977-01-01

    The safety strategy for nuclear power plants is characterized by the fact that the high level of safety was attained not as a result of experience, but on the basis of preventive accident analyses and the findings derived from such analyses. Although, in these accident analyses, the deterministic approach is predominant it is supplemented by reliability analyses. The accidents analyzed in nuclear licensing procedures cover a wide spectrum from minor incidents to the design basis accidents which determine the design of the safety devices. The initial and boundary conditions, which are essential for accident analyses, and the determination of the loads occuring in various states during regular operation and in accidents flow into the design of the individual systems and components. The inevitable residual risk and its origins are discussed. (orig./HP) [de

  6. Supplementary safety system 1/4 scale testing

    Energy Technology Data Exchange (ETDEWEB)

    Garrett, R.L.; Paik, I.K.

    1993-09-01

    During the course of updating the K-Reactor Safety Analysis Report Chapter 15 in 1990, it was identified that the current Supplementary Safety System (SSS) may not be adequate in protecting the reactor during the process water pump coastdown initiated by a loss of AC power when the safety rods are assumed to fail. A SSS modification project was initiated to add an additional ink injection pathway near the pump suction. In addition, the Department of Energy raised a question on the thermal buoyancy effects on moderator flow pattern and ink dispersion in the moderator space. The development and documentation of a two-dimensional code called MODFLOW was undertaken to describe the problem. This report discusses the results of the moderator flow and ink (Gadolinium Poison Solution - GPS) dispersion tests designed to provide qualified data for validation and benchmarking of the MODFLOW computer code with the secondary objectives being the development of concentration profiles and video footage of simulated GPS dispersion under steady-state and transient flow conditions.

  7. Improving resident engagement in quality improvement and patient safety initiatives at the bedside: the Advocate for Clinical Education (ACE).

    Science.gov (United States)

    Schleyer, Anneliese M; Best, Jennifer A; McIntyre, Lisa K; Ehrmantraut, Ross; Calver, Patty; Goss, J Richard

    2013-01-01

    Quality improvement (QI) and patient safety (PS) are essential competencies in residency training; however, the most effective means to engage physicians remains unclear. The authors surveyed all medicine and surgery physicians at their institution to describe QI/PS practices and concurrently implemented the Advocate for Clinical Education (ACE) program to determine if a physician-centered program in the context of educational structures and at the point of care improved performance. The ACE rounded with medicine and surgery teams and provided individual and team-level education and feedback targeting 4 domains: professionalism, infection control, interpreter use, and pain assessment. In a pilot, the ACE observed 2862 physician-patient interactions and 178 physicians. Self-reported compliance often was greater than the behaviors observed. Following ACE implementation, observed professionalism behaviors trended toward improvement; infection control also improved. Physicians were highly satisfied with the program. The ACE initiative is one coaching/feedback model for engaging residents in QI/PS that may warrant further study.

  8. Management and organization in nuclear power plant safety

    International Nuclear Information System (INIS)

    Osborn, R.N.

    1983-08-01

    In the immediate aftermath of the Three Mile Island accident, the Nuclear Regulatory Commission-sponsored investigations of the relation between human issues and safety tended to focus on individual and, at most, group level phenomena. This initial bottom up view of organizational safety has continued to be investigated by the Nuclear Regulatory Commission, as evidence by the four previous papers. Recently, however, work has begun which adopts a top down management/organization approach to nuclear power plant safety. This paper reports on the research, to date, on this focus

  9. Hawaii State Plan for Occupational Safety and Health. Final rule.

    Science.gov (United States)

    2012-09-21

    This document announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State Plan's ``final approval'' determination under Section 18(e) of the Occupational Safety and Health Act (the Act) and to transition to ``initial approval'' status. OSHA is reinstating concurrent federal enforcement authority over occupational safety and health issues in the private sector, which have been solely covered by the Hawaii State Plan since 1984.

  10. Culturally Safe Health Initiatives for Indigenous Peoples in Canada: A Scoping Review.

    Science.gov (United States)

    Brooks-Cleator, Lauren; Phillipps, Breanna; Giles, Audrey

    2018-01-01

    Background Cultural safety has the potential to improve the health disparities between Indigenous and non-Indigenous Canadians, yet practical applications of the concept are lacking in the literature. Purpose This study aims to identify the key components of culturally safe health initiatives for the Indigenous population of Canada to refine its application in health-care settings. Methods We conducted a scoping review of the literature pertaining to culturally safe health promotion programs, initiatives, services, or care for the Indigenous population in Canada. Our initial search yielded 501 publications, but after full review of 44 publications, 30 were included in the review. After charting the data, we used thematic analysis to identify themes in the data. Results We identified six themes: collaboration/partnerships, power sharing, address the broader context of the patient's life, safe environment, organizational and individual level self-reflection, and training for health-care providers. Conclusion While it is important to recognize that the provision of culturally safe initiatives depend on the specific interaction between the health-care provider and the patient, having a common understanding of the components of cultural safety, such as those that we identified through this research, will help in the transition of cultural safety from theory into practice.

  11. Improving patient safety: lessons from rock climbing.

    Science.gov (United States)

    Robertson, Nic

    2012-02-01

    How to improve patient safety remains an intractable problem, despite large investment and some successes. Academics have argued that the root of the problem is a lack of a comprehensive 'safety culture' in hospitals. Other safety-critical industries such as commercial aviation invest heavily in staff training to develop such a culture, but comparable programmes are almost entirely absent from the health care sector. In rock climbing and many other dangerous activities, the 'buddy system' is used to ensure that safety systems are adhered to despite adverse circumstances. This system involves two or more people using simple checks and clear communication to prevent problems causing harm. Using this system as an example could provide a simple, original and entertaining way of introducing medical students to the idea that human factors are central to ensuring patient safety. Teaching the buddy system may improve understanding and acceptance of other patient safety initiatives, and could also be used by junior doctors as a tool to improve the safety of their practice. © Blackwell Publishing Ltd 2012.

  12. SEAFP and SEAL: safety and environmental aspects

    International Nuclear Information System (INIS)

    Gulden, W.; Raeder, J.; Cook, I.

    2000-01-01

    The Safety and Environmental Assessment of Fusion Power (SEAFP) programme undertaken in the period 1992-1995 formed part of the ongoing effort in the European Fusion Programme to consider the safety and environmental aspects of fusion power. The assessment started with the development of a tokamak fusion power plant model of 3000 MW of fusion power. The analyses of safety included detailed consideration of effluents from normal operation, occupational doses, accidents (concentrating on the worst possible), and waste management. SEAFP was also the starting point for the Safety and Environmental Assessment of Fusion Power -- Long Term Programme (SEAL) initiated within the European Fusion Programme in 1995. SEAL aims at broadening the scope and elaborating selected aspects in more detail. SEAFP and SEAL confirmed the favourable safety and environmental characteristics of fusion power. They also confirmed the need to support these characteristics by dedicated materials development and safety-related design decisions. Recently, a new study on fusion safety (SEAFP-2) has been launched, defined for the time period 1997-1998, using SEAFP and SEAL findings as starting points

  13. APPROXIMATION OF THE TIME TO INITIATE THE EVACUATION

    Directory of Open Access Journals (Sweden)

    Jiří POKORNÝ

    2016-06-01

    Full Text Available One of the basic prerequisites for securing the safety of people at large group events is to ensure their evacuation in case of emergencies. This article deals with the approximations of time to initiate the evacuation of persons in case of a fire at large group events organized in outdoor spaces. The solution is based on the principles of determining the period to initiate the evacuation of persons in terms of international ISO standards. Considering the specificities of the given outdoor space and possible related security measures, the article recommends the relevant sufficient amount of time to initiate an evacuation.

  14. A new standard for multidisciplinary health and safety technicians

    International Nuclear Information System (INIS)

    Trinoskey, P.A.; Fry, L.A.; Egbert, W.F.

    2000-01-01

    Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

  15. A new standard for multidisciplinary health and safety technicians

    Energy Technology Data Exchange (ETDEWEB)

    Trinoskey, P.A.; Fry, L.A. [Lawrence Livermore National Laboratory, Univ. of California, CA (United States); Egbert, W.F. [Lawrence Livermore National Laboratory, Allied Signal Technical Corporation (United States)

    2000-05-01

    Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

  16. MAPLE-X10 reactor safety assessment

    International Nuclear Information System (INIS)

    Cotnam, K.D.; Lounsbury, R.I.; Gillespie, G.E.

    1990-01-01

    This paper reports on the safety assessment of the 10 MW MAPLE-X10 reactor which has involved a substantial component of PSA analysis to supplement deterministic analysis. Initiating events are identified through the use of a master logic diagram. The events are then examined through event sequence diagrams, at the concept design stage, followed by a set of reliability analyses that are coordinated with the event sequence diagrams. Improvements identified through the reliability analyses are incorporated into the design to ensure that safety objectives are attained

  17. The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

    2012-07-01

    The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

  18. Safety design guides for fire protection for CANDU 9

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

    1996-03-01

    This safety design guide establishes design requirements to ensure the radiological risk to the public due to fire is acceptable and operating personnel are adequately protected from the hazards of fires. This safety design guide also specifies the safety criteria for fire protection to be applied to mitigate fires and recommends the fire protection program to be established to initiate, coordinate and document the design activities associated with fire protection. The requirements for fire protection outlined in this safety design guide shall be satisfied in the design stage and the change status of the regulatory requirements, code and standards should be traced and incorporated into this safety design guide accordingly. 1 fig., (Author) .new

  19. Journey Toward High Reliability: A Comprehensive Safety Program to Improve Quality of Care and Safety Culture in a Large, Multisite Radiation Oncology Department.

    Science.gov (United States)

    Woodhouse, Kristina Demas; Volz, Edna; Maity, Amit; Gabriel, Peter E; Solberg, Timothy D; Bergendahl, Howard W; Hahn, Stephen M

    2016-05-01

    High-reliability organizations (HROs) focus on continuous identification and improvement of safety issues. We sought to advance a large, multisite radiation oncology department toward high reliability through the implementation of a comprehensive safety culture (SC) program at the University of Pennsylvania Department of Radiation Oncology. In 2011, with guidance from safety literature and experts in HROs, we designed an SC framework to reduce radiation errors. All state-reported medical events (SRMEs) from 2009 to 2016 were retrospectively reviewed and plotted on a control chart. Changes in SC grade were assessed using the Agency for Healthcare Research and Quality Hospital Survey. Outcomes measured included the number of radiation treatment fractions and days between SRMEs, as well as SC grade. Multifaceted safety initiatives were implemented at our main academic center and across all network sites. Postintervention results demonstrate increased staff fundamental safety knowledge, enhanced peer review with an electronic system, and special cause variation of SRMEs on control chart analysis. From 2009 to 2016, the number of days and fractions between SRMEs significantly increased, from a mean of 174 to 541 days (P safety framework. Our multifaceted initiatives, focusing on culture and system changes, can be successfully implemented in a large academic radiation oncology department to yield measurable improvements in SC and outcomes. Copyright © 2016 by American Society of Clinical Oncology.

  20. Fusion safety program annual report fiscal year 1997

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2)

  1. Fusion safety program annual report fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C. [and others

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2).

  2. Assessing medical students' perceptions of patient safety: the medical student safety attitudes and professionalism survey.

    Science.gov (United States)

    Liao, Joshua M; Etchegaray, Jason M; Williams, S Tyler; Berger, David H; Bell, Sigall K; Thomas, Eric J

    2014-02-01

    To develop and test the psychometric properties of a survey to measure students' perceptions about patient safety as observed on clinical rotations. In 2012, the authors surveyed 367 graduating fourth-year medical students at three U.S. MD-granting medical schools. They assessed the survey's reliability and construct and concurrent validity. They examined correlations between students' perceptions of organizational cultural factors, organizational patient safety measures, and students' intended safety behaviors. They also calculated percent positive scores for cultural factors. Two hundred twenty-eight students (62%) responded. Analyses identified five cultural factors (teamwork culture, safety culture, error disclosure culture, experiences with professionalism, and comfort expressing professional concerns) that had construct validity, concurrent validity, and good reliability (Cronbach alphas > 0.70). Across schools, percent positive scores for safety culture ranged from 28% (95% confidence interval [CI], 13%-43%) to 64% (30%-98%), while those for teamwork culture ranged from 47% (32%-62%) to 74% (66%-81%). They were low for error disclosure culture (range: 10% [0%-20%] to 27% [20%-35%]), experiences with professionalism (range: 7% [0%-15%] to 23% [16%-30%]), and comfort expressing professional concerns (range: 17% [5%-29%] to 38% [8%-69%]). Each cultural factor correlated positively with perceptions of overall patient safety as observed in clinical rotations (r = 0.37-0.69, P safety behavioral intent item. This study provided initial evidence for the survey's reliability and validity and illustrated its applicability for determining whether students' clinical experiences exemplify positive patient safety environments.

  3. Safety analysis of the proposed Canadian geologic nuclear waste repository

    International Nuclear Information System (INIS)

    Prowse, D.R.

    1977-01-01

    The Canadian program for development and qualification of a geologic repository for emplacement of high-level and long-lived, alpha-emitting waste from irradiated nuclear fuel has been inititiated and is in its initial development stage. Fieldwork programs to locate candidate sites with suitable geological characteristics have begun. Laboratory studies and development of models for use in safety analysis of the emplaced nuclear waste have been initiated. The immediate objective is to complete a simplified safety analysis of a model geologic repository by mid-1978. This analysis will be progressively updated and will form part of an environmental Assessment Report of a Model Fuel Center which will be issued in mid-1979. The long-term objectives are to develop advanced safety assessment models of a geologic repository which will be available by 1980

  4. Status report of the US Department of Energy's International Nuclear Safety Program

    International Nuclear Information System (INIS)

    1994-12-01

    The US Department of Energy (DOE) implements the US Government's International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program's activities that have been completed as of September 1994 and discusses those activities currently in progress

  5. NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

    International Nuclear Information System (INIS)

    Marshall, A.C.; Lee, J.H.; McCulloch, W.H.; Sawyer, J.C. Jr.; Bari, R.A.; Brown, N.W.; Cullingford, H.S.; Hardy, A.C.; Remp, K.; Sholtis, J.A.

    1992-01-01

    An Interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top- level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed

  6. Public safety around dams guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, T [Canadian Dam Association, Edmonton, AB (Canada)

    2010-07-01

    This presentation discussed Canadian and international initiatives for improving dam safety and described some of the drivers for the development of new Canadian Dam Association (CDA) public safety guidelines for dams. The CDA guidelines were divided into the following 3 principal sections: (1) managed system elements, (2) risk assessment and management, and (3) technical bulletins. Public and media responses to the drownings have called for improved safety guidelines. While the public remains unaware of the hazards of dams, public interaction with dams is increasing as a result of interest in extreme sports and perceived rights of access. Guidelines are needed for dam owners in order to provide due diligence. Various organizations in Canada are preparing technical and public safety dam guidelines. CDA guidelines have also been prepared for signage, booms and buoys, and audible and visual alerts bulletins. Working groups are also discussing recommended practices for spill procedures, spillways and the role of professional engineers in ensuring public safety. Methods of assessing risk were also reviewed. Managed system elements for risk assessment and public interactions were also discussed, and stepped control measures were presented. tabs., figs.

  7. EDF's nuclear safety approach for pressurized water reactors

    International Nuclear Information System (INIS)

    Tanguy, P.; Kus, J.P.

    1987-01-01

    The realization of the important French program fifty-four units equipped with pressurized water reactors in service, or under construction-had led to the progressive implementation of an original approach in the field of nuclear safety. From an initial core consisting of the deterministic approach to safety devised on the other side of the Atlantic, which has been entirely preserved and often specified, further extras have been added which overall increase the level of safety of the installations, without any particular complications. This paper aims at presenting succinctly the outcome of the deliberation, which constitutes now the approach adopted by Electricite de France for the safety of nuclear units equipped with pressurized water reactors. This approach is explained in more detail in EDF's 'with book' on nuclear safety. (author)

  8. EDF'S nuclear safety approach for pressurized water reactors

    International Nuclear Information System (INIS)

    Tanguy, P.; Kus, J.P.

    1988-01-01

    The realization of the important French program fifty-four units equipped with pressurized water reactors in service, or under construction - had led to the progressive implementation of an original approach in the field of nuclear safety. From an initial core consisting of the deterministic approach to safety devised on the other side of the Atlantic, which has been entirely preserved and often specified, further extras have been added which overall increase the level of safety of the installations, without any particular complications. This paper aims at presenting succinctly the outcome of the deliberation, which constitutes now the approach adopted by Electricite de France for the safety of nuclear units equipped with pressurized water reactors. This approach is explained in more detail in EDF's white book on nuclear safety

  9. Initial Demonstration of the Real-Time Safety Monitoring Framework for the National Airspace System Using Flight Data

    Science.gov (United States)

    Roychoudhury, Indranil; Daigle, Matthew; Goebel, Kai; Spirkovska, Lilly; Sankararaman, Shankar; Ossenfort, John; Kulkarni, Chetan; McDermott, William; Poll, Scott

    2016-01-01

    As new operational paradigms and additional aircraft are being introduced into the National Airspace System (NAS), maintaining safety in such a rapidly growing environment becomes more challenging. It is therefore desirable to have an automated framework to provide an overview of the current safety of the airspace at different levels of granularity, as well an understanding of how the state of the safety will evolve into the future given the anticipated flight plans, weather forecast, predicted health of assets in the airspace, and so on. Towards this end, as part of our earlier work, we formulated the Real-Time Safety Monitoring (RTSM) framework for monitoring and predicting the state of safety and to predict unsafe events. In our previous work, the RTSM framework was demonstrated in simulation on three different constructed scenarios. In this paper, we further develop the framework and demonstrate it on real flight data from multiple data sources. Specifically, the flight data is obtained through the Shadow Mode Assessment using Realistic Technologies for the National Airspace System (SMART-NAS) Testbed that serves as a central point of collection, integration, and access of information from these different data sources. By testing and evaluating using real-world scenarios, we may accelerate the acceptance of the RTSM framework towards deployment. In this paper we demonstrate the framework's capability to not only estimate the state of safety in the NAS, but predict the time and location of unsafe events such as a loss of separation between two aircraft, or an aircraft encountering convective weather. The experimental results highlight the capability of the approach, and the kind of information that can be provided to operators to improve their situational awareness in the context of safety.

  10. Code of safety for nuclear merchant ships

    International Nuclear Information System (INIS)

    1982-01-01

    The Code is in chapters, entitled: general (including general safety principles and principles of risk acceptance); design criteria and conditions; ship design, construction and equipment; nuclear steam supply system; machinery and electrical installations; radiation safety (including radiological protection design; protection of persons; dosimetry; radioactive waste management); operation (including emergency operation procedures); surveys. Appendices cover: sinking velocity calculations; seaway loads depending on service periods; safety assessment; limiting dose-equivalent rates for different areas and spaces; quality assurance programme; application of single failure criterion. Initial application of the Code is restricted to conventional types of ships propelled by nuclear propulsion plants with pressurized light water type reactors. (U.K.)

  11. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2006-03-15

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  12. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2006-03-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  13. Research on Initiation Sensitivity of Solid Explosive and Planer Initiation System

    Directory of Open Access Journals (Sweden)

    N Matsuo

    2016-09-01

    Full Text Available Firstly, recently, there are a lot of techniques being demanded for complex process, various explosive initiation method and highly accurate control of detonation are needed. In this research, the metal foil explosion using high current is focused attention on the method to obtain linear or planate initiation easily, and the main evaluation of metal foil explosion to initiate explosive was conducted. The explosion power was evaluated by observing optically the underwater shock wave generated from the metal foil explosion. Secondly, in high energy explosive processing, there are several applications, such as shock compaction, explosive welding, food processing and explosive forming. In these explosive applications, a high sensitive explosive has been mainly used. The high sensitive explosive is so dangerous, since it can lead to explosion suddenly. So, for developing explosives, the safety is the most important thing as well as low manufacturing cost and explosive characteristics. In this work, we have focused on the initiation sensitivity of a solid explosive and performed numerical analysis of sympathetic detonation. The numerical analysis is calculated by LS-DYNA 3D (commercial code. To understand the initiation reaction of an explosive, Lee-Tarver equation was used and impact detonation process was analyzed by ALE code. Configuration of simulation model is a quarter of circular cylinder. The donor type of explosive (SEP was used as initiation explosive. When the donor explosive is exploded, a shock wave is generated and it propagates into PMMA, air and metallic layers in order. During passing through the layers, the shock wave is attenuated and finally, it has influence on the acceptor explosive, Comp. B. Here, we evaluate the initiation of acceptor explosive and discuss about detonation pressure, reactive rate of acceptor explosive and attenuation of impact pressure.

  14. Passive components of NPP safety-related systems

    International Nuclear Information System (INIS)

    Ionaytis Romuald, R.; Bubnova Tatyana, A.

    2005-01-01

    This paper presents a new passive components with having drives: fast-response cutoff valves; modular actuators with opposite cocking pneumatic drives and actuation spring drives; voting electromagnetic valve units for control of pneumatic drives; passive initiators of actuation; visual diagnostics . All these devices have been developed and tested at mock-ups. This paper presents also the following direct-action passive safety components: modular pressure-relief safety valves; pilot safety valves with passive action; check valves with remote position indicator and after-tightening; modular inserts for limiting emergency coolant flow; vortex rectifier; critical weld fasteners; gas-liquid valves; fast-removable seal assembly; seal spring loaders; grooves for increasing hydraulic resistance. Replacement of active safety system components for passive ones improves the general reliability NPP by 1.5 or 2 orders of magnitudes. (authors)

  15. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  16. Ergonomic initiatives at Inmetro: measuring occupational health and safety.

    Science.gov (United States)

    Drucker, L; Amaral, M; Carvalheira, C

    2012-01-01

    This work studies biomechanical hazards to which the workforce of Instituto Nacional de Metrologia, Qualidade e Tecnologia Industrial (Inmetro) is exposed. It suggests a model for ergonomic evaluation of work, based on the concepts of resilience engineering which take into consideration the institute's ability to manage risk and deal with its consequences. Methodology includes the stages of identification, inventory, analysis, and risk management. Diagnosis of the workplace uses as parameters the minimal criteria stated in Brazilian legislation. The approach has several prospectives and encompasses the points of view of public management, safety engineering, physical therapy and ergonomics-oriented design. The suggested solution integrates all aspects of the problem: biological, psychological, sociological and organizational. Results obtained from a pilot Project allow to build a significant sample of Inmetro's workforce, identifying problems and validating the methodology employed as a tool to be applied to the whole institution. Finally, this work intends to draw risk maps and support goals and methods based on resiliency engineering to assess environmental and ergonomic risk management.

  17. Environmental, health, and safety by design

    International Nuclear Information System (INIS)

    Soklow, R.G.

    1999-01-01

    Solar Turbines Incorporated created a self-directed work team, the Safety and Environmental Awareness (SEA) Team that initiated a company wide effort to raise employee awareness to promote integrating responsible environmental, health, and safety practices into product design, manufacturing, and services. Environmental, health, and safety issues influence how all businesses operate around the world. Companies choose to operate in an environmentally responsible manner because it not only benefits employees and the communities where they live, it also benefits the business when superior performance results in a competitive advantage. Solar surveyed gas turbines users to identify their top environmental and safety concerns and issues. The authors asked about various environmental and safety aspects of their equipment. Results from the survey has helped engineering and design focus efforts so that future products and product improvements assist customers in meeting their regulatory obligations and social responsibilities. Air pollution has historically been one of the most important environmental issues facing customers, because pollutant emissions greatly influence equipment choices and operation flexibility. There are other environmental, health and safety issues: sustainable fire suppression choices, start systems, hazardous materials use and ability to recycle materials, package accessibility, noise and product take back issues

  18. Developing safety culture in nuclear power engineering

    International Nuclear Information System (INIS)

    Tevlin, S.A.

    2000-01-01

    The new issue (no. 11) of the IAEA publications series Safety Reports, devoted to the safety culture in nuclear engineering Safety culture development in the nuclear activities. Practical recommendations to achieve success, is analyzed. A number of recommendations of international experts is presented and basic general indicators of satisfactory and insufficient safety culture in the nuclear engineering are indicated. It is shown that the safety culture has two foundations: human behavior and high quality of the control system. The necessity of creating the confidence by the management at all levels of the enterprise, development of individual initiative and responsibility of the workers, which make it possible to realize the structural hierarchic system, including technical, human and organizational constituents, is noted. Three stages are traced in the process of introducing the safety culture. At the first stage the require,emts of scientific-technical documentation and provisions of the governmental, regional and control organs are fulfilled. At the second stage the management of the organization accepts the safety as an important direction in its activities. At the third stage the organization accomplishes its work, proceeding from the position of constant safety improvement. The general model of the safety culture development is considered [ru

  19. PUREX Deactivation Health and Safety documentation

    Energy Technology Data Exchange (ETDEWEB)

    Dodd, E.N. III

    1995-01-01

    The purpose of the PUREX Deactivation Project is to establish a passively safe and environmentally secure configuration of PUREX at the Hanford Site, and to preserve that configuration for a 10-year horizon. The 10-year horizon is used to predict future maintenance requirements and represents they typical time duration expended to define, authorize, and initiate the follow-on Decontamination and Decommissioning (D&D) activities. This document was prepared to increase attention to worker safety issues during the deactivation project and, as such, identifies the documentation and programs associated with PUREX Deactivation Health and Safety.

  20. Westinghouse Advances in Passive Plant Safety

    International Nuclear Information System (INIS)

    Bruschi, H. J.; Manager, General; Gerstenhaber, E.

    1993-01-01

    On June 26, 1992, Westinghouse submitted the Ap600 Standard Safety Analysis Report and comprehensive PIRA results to the U. S. NRC for review as part of the Ap600 design certification program. This major milestone was met on time on a schedule set more than 3 years before submittal and is the result of the cooperative efforts of the U. S. Department of Energy (DOE), the Electric Power Requirements Program, and the Westinghouse Ap600 design team. These efforts were initiated in 1985 to develop a 600 MW advanced light water reactor plant design based on specific technical requirements established to provide the safety, simplicity, reliability, and economics necessary for the next generation of nuclear power plants. The Ap600 design achieves the ALRR safety requirements through ample design margins, simplified safety systems based on natural driving forces, and on a human-engineered man-machine interface system. Extensive Probabilistic Risk evolution, have recently shown that even if none of the active defense-in-depth safety systems are available, the passive systems alone meet safety goals. Furthermore, many tests in an extensive test program have begun or have been completed. Early tests show that passive safety perform well and meet design expectations

  1. Fusion Safety Program Annual Report, Fiscal Year 1996

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1996-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

  2. Model quality and safety studies

    DEFF Research Database (Denmark)

    Petersen, K.E.

    1997-01-01

    The paper describes the EC initiative on model quality assessment and emphasizes some of the problems encountered in the selection of data from field tests used in the evaluation process. Further, it discusses the impact of model uncertainties in safety studies of industrial plants. The model...... that most of these have never been through a procedure of evaluation, but nonetheless are used to assist in making decisions that may directly affect the safety of the public and the environment. As a major funder of European research on major industrial hazards, DGXII is conscious of the importance......-tain model is appropriate for use in solving a given problem. Further, the findings from the REDIPHEM project related to dense gas dispersion will be highlighted. Finally, the paper will discuss the need for model quality assessment in safety studies....

  3. Hospital safety culture in Taiwan: a nationwide survey using Chinese version Safety Attitude Questionnaire.

    Science.gov (United States)

    Lee, Wui-Chiang; Wung, Hwei-Ying; Liao, Hsun-Hsiang; Lo, Chien-Ming; Chang, Fei-Ling; Wang, Pa-Chun; Fan, Angela; Chen, Hsin-Hsin; Yang, Han-Chuan; Hou, Sheng-Mou

    2010-08-10

    Safety activities have been initiated at many hospitals in Taiwan, but little is known about the safety culture at these hospitals. The aims of this study were to verify a safety culture survey instrument in Chinese and to assess hospital safety culture in Taiwan. The Taiwan Patient Safety Culture Survey was conducted in 2008, using the adapted Safety Attitude Questionnaire in Chinese (SAQ-C). Hospitals and their healthcare workers participated in the survey on a voluntary basis. The psychometric properties of the five SAQ-C dimensions were examined, including teamwork climate, safety climate, job satisfaction, perception of management, and working conditions. Additional safety measures were asked to assess healthcare workers' attitudes toward their collaboration with nurses, physicians, and pharmacists, respectively, and perceptions of hospitals' encouragement of safety reporting, safety training, and delivery delays due to communication breakdowns in clinical areas. The associations between the respondents' attitudes to each SAQ-C dimension and safety measures were analyzed by generalized estimating equations, adjusting for the clustering effects at hospital levels. A total of 45,242 valid questionnaires were returned from 200 hospitals with a mean response rate of 69.4%. The Cronbach's alpha was 0.792 for teamwork climate, 0.816 for safety climate, 0.912 for job satisfaction, 0.874 for perception of management, and 0.785 for working conditions. Confirmatory factor analyses demonstrated a good model fit for each dimension and the entire construct. The percentage of hospital healthcare workers holding positive attitude was 48.9% for teamwork climate, 45.2% for perception of management, 42.1% for job satisfaction, 37.2% for safety climate, and 31.8% for working conditions. There were wide variations in the range of SAQ-C scores in each dimension among hospitals. Compared to those without positive attitudes, healthcare workers with positive attitudes to each SAQ

  4. A review for identification of initiating events in event tree development process on nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Riyadi, Eko H., E-mail: e.riyadi@bapeten.go.id [Center for Regulatory Assessment of Nuclear Installation and Materials, Nuclear Energy Regulatory Agency (BAPETEN), Jl. Gajah Mada 8 Jakarta 10120 (Indonesia)

    2014-09-30

    Initiating event is defined as any event either internal or external to the nuclear power plants (NPPs) that perturbs the steady state operation of the plant, if operating, thereby initiating an abnormal event such as transient or loss of coolant accident (LOCA) within the NPPs. These initiating events trigger sequences of events that challenge plant control and safety systems whose failure could potentially lead to core damage or large early release. Selection for initiating events consists of two steps i.e. first step, definition of possible events, such as by evaluating a comprehensive engineering, and by constructing a top level logic model. Then the second step, grouping of identified initiating event's by the safety function to be performed or combinations of systems responses. Therefore, the purpose of this paper is to discuss initiating events identification in event tree development process and to reviews other probabilistic safety assessments (PSA). The identification of initiating events also involves the past operating experience, review of other PSA, failure mode and effect analysis (FMEA), feedback from system modeling, and master logic diagram (special type of fault tree). By using the method of study for the condition of the traditional US PSA categorization in detail, could be obtained the important initiating events that are categorized into LOCA, transients and external events.

  5. The Cultural Adaptation of a Community-Based Child Maltreatment Prevention Initiative.

    Science.gov (United States)

    McLeigh, Jill D; Katz, Carmit; Davidson-Arad, Bilha; Ben-Arieh, Asher

    2017-06-01

    A unique primary prevention effort, Strong Communities for Children (Strong Communities), focuses on changing attitudes and expectations regarding communities' collective responsibilities for the safety of children. Findings from a 6-year pilot of the initiative in South Carolina have shown promise in reducing child maltreatment, but efforts to adapt the initiative to different cultural contexts have been lacking. No models exist for adapting an initiative that takes a community-level approach to ensuring children's safety. Thus, this article addresses the gap by providing an overview of the original initiative, how the initiative was adapted to the Israeli context, and lessons learned from the experience. Building on conceptualizations of cultural adaptation by Castro et al. (Prevention Science, 5, 2004, 41) and Resnicow et al. (Ethnicity and Disease, 9, 1999, 11), sources of nonfit (i.e., sociodemographic traits, political conflict, government services, and the presence and role of community organizations) were identified and deep and surface structure modifications were made to the content and delivery. Ultimately, this article describes the adaption and dissemination of a community-based child maltreatment prevention initiative in Tel Aviv, Israel, and addresses researchers' calls for more publications describing the adaptation of interventions and the procedures that need to be implemented to achieve cultural relevance. © 2015 Family Process Institute.

  6. Application of a model for delivering occupational safety and health to smaller businesses: Case studies from the US.

    Science.gov (United States)

    Cunningham, Thomas R; Sinclair, Raymond

    2015-01-01

    Smaller firms are the majority in every industry in the US, and they endure a greater burden of occupational injuries, illnesses, and fatalities than larger firms. Smaller firms often lack the necessary resources for effective occupational safety and health activities, and many require external assistance with safety and health programming. Based on previous work by researchers in Europe and New Zealand, NIOSH researchers developed for occupational safety and health intervention in small businesses. This model was evaluated with several intermediary organizations. Four case studies which describe efforts to reach small businesses with occupational safety and health assistance include the following: trenching safety training for construction, basic compliance and hazard recognition for general industry, expanded safety and health training for restaurants, and fall prevention and respirator training for boat repair contractors. Successful efforts included participation by the initiator among the intermediaries' planning activities, alignment of small business needs with intermediary offerings, continued monitoring of intermediary activities by the initiator, and strong leadership for occupational safety and health among intermediaries. Common challenges were a lack of resources among intermediaries, lack of opportunities for in-person meetings between intermediaries and the initiator, and balancing the exchanges in the initiator-intermediary-small business relationships. The model offers some encouragement that initiator organizations can contribute to sustainable OSH assistance for small firms, but they must depend on intermediaries who have compatible interests in smaller businesses and they must work to understand the small business social system.

  7. Technical safety appraisal of the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    1992-05-01

    On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

  8. Reliability analysis of diverse safety logic systems of fast breeder reactor

    International Nuclear Information System (INIS)

    Ravi Kumar, Bh.; Apte, P.R.; Srivani, L.; Ilango Sambasivan, S.; Swaminathan, P.

    2006-01-01

    Safety Logic for Fast Breeder Reactor (FBR) is designed to initiate safety action against Design Basis Events. Based on the outputs of various processing circuits, Safety logic system drives the control rods of the shutdown system. So, Safety Logic system is classified as safety critical system. Therefore, reliability analysis has to be performed. This paper discusses the Reliability analysis of Diverse Safety logic systems of FBRs. For this literature survey on safety critical systems, system reliability approach and standards to be followed like IEC-61508 are discussed in detail. For Programmable Logic device based systems, Hardware Description Languages (HDL) are used. So this paper also discusses the Verification and Validation for HDLs. Finally a case study for the Reliability analysis of Safety logic is discussed. (author)

  9. Safety Training: places available in March 2014

    CERN Multimedia

    Safety Training team, HSE Unit

    2014-01-01

    There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   March 2014 (alphabetical order) Ergonomics - Worksite and Workshop 24-MAR-14, 9.00 – 17.30, in French Fire Extinguisher 05-MAR-14, 10.30 – 12.00, in French 12-MAR-14, 8.30 – 10.00, in English 12-MAR-14, 10.30 – 12.00, in English First Aider - Level 1 – Initial 27-MAR-14, 8.30 – 17.30, in English First Aider – Refresher 20-MAR-14, 8.30 – 12.30, in French 20-MAR-14, 13.30 – 17.30, in French Habilitation électrique - Electrician Low Voltage – Initial 17-MAR-14 to 19-MAR-14, 9.00 – 17.30, in French 24-MAR-14 to 26-MAR-14, 9.00 – 17.30, in English Habilitation électrique - Electrician Low and High Voltage – Initial 18-MAR-14 to 21-MAR-14, 9.00 – 17.30, in English Habilitation &eacut...

  10. Safety Training: places available in January 2014

    CERN Multimedia

    Safety Training Team, HSE Unit

    2014-01-01

    There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   January 2014 (alphabetical order) Confined space 28-JAN-14, 9.00 – 17.30, in French Ergonomics – Office 30-JAN-14, 9.00 – 12.00, in French Fire Extinguisher 08-JAN-14, 10.30 – 12.00, in French 24-JAN-14, 10.30 – 12.00, in English 31-JAN-14, 10.30 – 12.00, in French First Aider - Level 1 – Initial 16-JAN-14, 8.30 – 17.30, in French 30-JAN-14, 8.30 – 17.30, in French First Aider – Refresher 09-JAN-14, 8.30 – 12.30, in French 09-JAN-14, 13.30 – 17.30, in French Habilitation électrique - Electrician Low Voltage - Initial 22-JAN-14 au 24-JAN-14, 9.00 – 17.30, in English Habilitation électrique - Electrician Low and High Voltage - Initial 28-JAN-14 au 31-JAN-14, 9.00 – 17.30, in French ...

  11. Safety Training: places available in January 2014

    CERN Document Server

    Safety Training Team, HSE Unit

    2013-01-01

    There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   January 2014 (alphabetical order) Confined space 28-JAN-14, 9.00 – 17.30, in French Ergonomics – Office 30-JAN-14, 9.00 – 12.00, in French Fire Extinguisher 08-JAN-14, 10.30 – 12.00, in French 24-JAN-14, 10.30 – 12.00, in English 31-JAN-14, 10.30 – 12.00, in French First Aider - Level 1 – Initial 16-JAN-14, 8.30 – 17.30, in French 30-JAN-14, 8.30 – 17.30, in French First Aider – Refresher 09-JAN-14, 8.30 – 12.30, in French 09-JAN-14, 13.30 – 17.30, in French Habilitation électrique - Electrician Low Voltage - Initial 22-JAN-14 au 24-JAN-14, 9.00 – 17.30, in English Habilitation électrique - Electrician Low and High Voltage - Initial 28-JAN-14 au 31-JAN-14, 9.00 – 17.30, in French ...

  12. Plant designer's view of the operator's role in nuclear plant safety

    International Nuclear Information System (INIS)

    Corcoran, W.R.; Church, J.F.; Cross, M.T.; Porter, N.J.

    1981-01-01

    The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

  13. Safety assessment for the IS process in a hydrogen production facility

    International Nuclear Information System (INIS)

    Cho, Nam Chul

    2005-08-01

    A substitute energy development have been required due to the dry up of the fossil fuel and an environmental problem. Consequently, among substitute energy to be discussed, producing hydrogen from water which does not release carbon is a very promising technology. Also, Iodine-Sulfur(IS) thermochemical water decomposition is one of the promising process which is used to produce hydrogen efficiently using the high temperature gas-cooled reactor(HTGR) as an energy source that is possible to supply heat over 1000 .deg. C. In this study, to make a safety assessment of the hydrogen production using the IS process, an initiating events analysis and an accident scenario modeling considering the relief system were carried out. A method for initiating event identification used the Master Logic Diagram(MLD) that is logical and deductive. As a result, 9 initiating events that cause a leakage of the chemical material were identified. 6 accident scenario based on the initiating event are identified and quantified to the event trees. The frequency of the chemical material leakage produced by IS process is estimated relatively high to the value of 1.22x10 -4 /y. Therefore, it requires more effort on safety of the hydrogen production which can be considered as a part of the nuclear system and safety management research to increase social acceptability. Moreover, these methods will be helpful to the safety assessment of the hydrogen production system of the IS process in general

  14. 49 CFR 238.105 - Train electronic hardware and software safety.

    Science.gov (United States)

    2010-10-01

    ... and software system safety as part of the pre-revenue service testing of the equipment. (d)(1... safely by initiating a full service brake application in the event of a hardware or software failure that... 49 Transportation 4 2010-10-01 2010-10-01 false Train electronic hardware and software safety. 238...

  15. 1982 annual status report: reactor safety

    International Nuclear Information System (INIS)

    1982-01-01

    This report presents the projects of the Reactor Safety Program at the JRC: 1) Reliability and risk evolution; 2) LWR loss of coolant accident studies; 3) Primary system integrity; 4) LMFBR core accident initiation and transition phase; and, 5) LMFBR accident post disassembly phase

  16. A holistic view on Safety Management

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    to prevent accidents is to identify the risks in all kinds of situations and take precautions by establishing safety barriers either technically or by improving the processes involved in managing these barriers, as well as bringing about behavioral improvements through good leadership. A project initiated...

  17. Evaluation of the League General Insurance Company child safety seat distribution program

    Science.gov (United States)

    1982-05-01

    This report presents an evaluation of the child safety seat distribution initiated by the League General Insurance Company in June 1979. The program provides child safety seats as a benefit under the company's auto insurance policies to policy-holder...

  18. Initial assessment of MHTGR confinement releases

    International Nuclear Information System (INIS)

    Maneke, J.L.; Lanning, D.D.; Lidsky, L.M.

    1986-01-01

    Initial investigation of Modular High Temperature Gas-Cooled Reactor (MHTGR) designs suggest that source terms during postulated accidents will be considerably lower than Light Water Reactor (LWR) source term estimates. These lower postulated accident releases are not only a safety incentive, but also an economic incentive for the development of this reactor type. For example, it is hoped that a filtered confinement building, rather than a more expensive LWR-like containment building, would adequately protect the public from radiological releases. The ability of a confinement building to satisfy safety requirements for the MHTGR depends on several reactor parameters, such as fuel quality, reactor design, and the design of the reactor building. SCIMCA, a Simple Code for Initial MHTGR Confinement Assessment has been developed for preliminary MHTGR building requirement calculations. The code is capable of modeling a decay chain with a maximum of five regions. Phenomena such as fission product decay and buildup, natural deposition, building filtration, and intercompartmental transport are incorporated. SCIMCA models reduction mechanisms, such as dispersion and decay, occurring as radioactivity is transported through the environment. A subroutine for calculating doses at specified distances has also been included

  19. 78 FR 9623 - Federal Motor Vehicle Safety Standards; Air Brake Systems

    Science.gov (United States)

    2013-02-11

    ... initial speeds, vehicle manufacturers will need to develop unique or complicated braking systems to comply... [Docket No. NHTSA-2013-0011] RIN 2127-AL11 Federal Motor Vehicle Safety Standards; Air Brake Systems... rule that amended the Federal motor vehicle safety standard for air brake systems by requiring...

  20. Fusion Safety Program annual report, fiscal year 1994

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities

  1. Smart roadside initiative gap analysis : trucking technology literature review.

    Science.gov (United States)

    2014-04-01

    The Smart Roadside Initiative (SRI) was designed to breakdown information silos at the roadside in order to improve : motor carrier safety and mobility, as well as the operational efficiency of motor carriers and the public-sector agencies : that reg...

  2. Nuclear safety improvement activities related to WWER-440 units in Bulgaria

    International Nuclear Information System (INIS)

    Gantchev, T.

    1998-01-01

    The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

  3. Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

  4. Chemical Safety Vulnerability Working Group report. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports.

  5. Chemical Safety Vulnerability Working Group report. Volume 3

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports

  6. Application of precursor methodology in initiating frequency estimates

    International Nuclear Information System (INIS)

    Kohut, P.; Fitzpatrick, R.G.

    1991-01-01

    The precursor methodology developed in recent years provides a consistent technique to identify important accident sequence precursors. It relies on operational events (extracting information from actual experience) and infers core damage scenarios based on expected safety system responses. The ranking or categorization of each precursor is determined by considering the full spectrum of potential core damage sequences. The methodology estimates the frequency of severe core damage based on the approach suggested by Apostolakis and Mosleh, which may lead to a potential overestimation of the severe-accident sequence frequency due to the inherent dependencies between the safety systems and the initiating events. The methodology is an encompassing attempt to incorporate most of the operating information available from nuclear power plants and is an attractive tool from the point of view of risk management. In this paper, a further extension of this methodology is discussed with regard to the treatment of initiating frequency of the accident sequences

  7. Traffic & safety statewide model and GIS modeling.

    Science.gov (United States)

    2012-07-01

    Several steps have been taken over the past two years to advance the Utah Department of Transportation (UDOT) safety initiative. Previous research projects began the development of a hierarchical Bayesian model to analyze crashes on Utah roadways. De...

  8. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance.

  9. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    International Nuclear Information System (INIS)

    1978-01-01

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance

  10. Using Contemporary Leadership Skills in Medication Safety Programs.

    Science.gov (United States)

    Hertig, John B; Hultgren, Kyle E; Weber, Robert J

    2016-04-01

    The discipline of studying medication errors and implementing medication safety programs in hospitals dates to the 1970s. These initial programs to prevent errors focused only on pharmacy operation changes - and not the broad medication use system. In the late 1990s, research showed that faulty systems, and not faulty people, are responsible for errors and require a multidisciplinary approach. The 2013 ASHP Statement on the Role of the Medication Safety Leader recommended that medication safety leaders be integrated team members rather than a single point of contact. Successful medication safety programs must employ a new approach - one that embraces the skills of all health care team members and positions many leaders to improve safety. This approach requires a new set of leadership skills based on contemporary management principles, including followership, team-building, tracking and assessing progress, storytelling and communication, and cultivating innovation, all of which promote transformational change. The application of these skills in developing or changing a medication safety program is reviewed in this article.

  11. Containment safety margins

    International Nuclear Information System (INIS)

    Von Riesemann, W.A.

    1980-01-01

    Objective of the Containment Safety Margins program is the development and verification of methodologies which are capable of reliably predicting the ultimate load-carrying capability of light water reactor containment structures under accident and severe environments. The program was initiated in June 1980 at Sandia and this paper addresses the first phase of the program which is essentially a planning effort. Brief comments are made about the second phase, which will involve testing of containment models

  12. Toward a Safety Risk-Based Classification of Unmanned Aircraft

    Science.gov (United States)

    Torres-Pomales, Wilfredo

    2016-01-01

    There is a trend of growing interest and demand for greater access of unmanned aircraft (UA) to the National Airspace System (NAS) as the ongoing development of UA technology has created the potential for significant economic benefits. However, the lack of a comprehensive and efficient UA regulatory framework has constrained the number and kinds of UA operations that can be performed. This report presents initial results of a study aimed at defining a safety-risk-based UA classification as a plausible basis for a regulatory framework for UA operating in the NAS. Much of the study up to this point has been at a conceptual high level. The report includes a survey of contextual topics, analysis of safety risk considerations, and initial recommendations for a risk-based approach to safe UA operations in the NAS. The next phase of the study will develop and leverage deeper clarity and insight into practical engineering and regulatory considerations for ensuring that UA operations have an acceptable level of safety.

  13. Fuel safety research 2000

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

  14. LearnSafe. Learning organisations for nuclear safety

    International Nuclear Information System (INIS)

    Wahlstroem, B.; Kettunen, J.; Reiman, T.

    2005-03-01

    The nuclear power industry is currently undergoing a period of major change, which has brought with it a number of challenges. These changes have forced the nuclear power plants to initiate their own processes of change in order to adapt to the new situation. This adaptation must not compromise safety at any time, but during a rapid process of change there is a danger that minor problems may trigger a chain of events leading to a degraded safety. Organisational learning has been identified as an important component in ensuring the continued safety and efficiency of nuclear organisations. In response to these challenges a project LearnSafe 'Learning organisations for nuclear safety' was set up and funded by the European Community under the 5th Euratom Framework Programme. The present report gives an account of the LearnSafe project and its major results. (orig.)

  15. Organizational culture and nuclear safety

    International Nuclear Information System (INIS)

    Germann, R.P.

    1990-01-01

    GPU Nuclear has become increasingly aware of the impact of culture on performance and therefore on nuclear safety. Culture is simply described as the way things are done around here. Senior management has developed a mission and a vision and values statement to guide this culture change. The company has embarked on a number of culture-influencing initiatives, including teamwork and leadership, the subject of this paper. This paper notes the functional initiatives that were one aspect of the evolution of the overall program. These functional initiatives were requests from line managers for assistance from in-house facilitators to help their areas become even more effective. Also, the overall program implementation has evolved to include use of additional materials and concepts

  16. Aligning institutional priorities: engaging house staff in a quality improvement and safety initiative to fulfill Clinical Learning Environment Review objectives and electronic medical record Meaningful Use requirements.

    Science.gov (United States)

    Flanagan, Meghan R; Foster, Carolyn C; Schleyer, Anneliese; Peterson, Gene N; Mandell, Samuel P; Rudd, Kristina E; Joyner, Byron D; Payne, Thomas H

    2016-02-01

    House staff quality improvement projects are often not aligned with training institution priorities. House staff are the primary users of inpatient problem lists in academic medical centers, and list maintenance has significant patient safety and financial implications. Improvement of the problem list is an important objective for hospitals with electronic health records under the Meaningful Use program. House staff surveys were used to create an electronic problem list manager (PLM) tool enabling efficient problem list updating. Number of new problems added and house staff perceptions of the problem list were compared before and after PLM intervention. The PLM was used by 654 house staff after release. Surveys demonstrated increased problem list updating (P = .002; response rate 47%). Mean new problems added per day increased from 64 pre-PLM to 125 post-PLM (P house staff in institutional quality and safety initiatives with tangible institutional benefits. Copyright © 2016 Elsevier Inc. All rights reserved.

  17. Fusion Safety Program annual report, Fiscal Year 1993

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1993-12-01

    This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

  18. Identification of common cause initiators in IRS database

    Energy Technology Data Exchange (ETDEWEB)

    Nyman, R. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Kulig, M.; Tomic, B. [ENCONET Consulting GmbH, Vienna (Austria)

    1998-02-01

    The objective of this project is to obtain practical insights relevant for the identification of Common Cause Initiators (CCIs) based on event data available in the NEA Incident Reporting System. The project is intended to improve the understanding of CCIs and, in consequence, their consideration in safety assessment of nuclear power plants and in particular plant specific probabilistic safety assessment. The project is a pilot study, and not expected to provide answers for all related questions. Its scope is limited to some practical insights that would help to improve the understanding of the issue and to establish directions for further work.

  19. Identification of common cause initiators in IRS database

    International Nuclear Information System (INIS)

    Nyman, R.; Kulig, M.; Tomic, B.

    1998-02-01

    The objective of this project is to obtain practical insights relevant for the identification of Common Cause Initiators (CCIs) based on event data available in the NEA Incident Reporting System. The project is intended to improve the understanding of CCIs and, in consequence, their consideration in safety assessment of nuclear power plants and in particular plant specific probabilistic safety assessment. The project is a pilot study, and not expected to provide answers for all related questions. Its scope is limited to some practical insights that would help to improve the understanding of the issue and to establish directions for further work

  20. Categorization of Radioactive Sources. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  1. 30 CFR 57.6502 - Safety fuse.

    Science.gov (United States)

    2010-07-01

    ... blasthole detonates. (d) Fuse shall be cut and capped in dry locations. (e) Blasting caps shall be crimped... the primer and the explosive material are securely in place. (g) Safety fuse shall be ignited only... to be fired, electric initiation systems, igniter cord and connectors, or other nonelectric...

  2. Advancing perinatal patient safety through application of safety science principles using health IT.

    Science.gov (United States)

    Webb, Jennifer; Sorensen, Asta; Sommerness, Samantha; Lasater, Beth; Mistry, Kamila; Kahwati, Leila

    2017-12-19

    into materials to facilitate the implementation of perinatal safety initiatives.

  3. The nuclear power safety programme of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Rosen, M.

    1981-01-01

    The role of the International Atomic Energy Agency in the field of nuclear power safety is growing. In the period since the Three Mile Island accident, a significant expansion in its nuclear safety programme has taken place. To assure an acceptable safety level world-wide, new emphasis is being placed on the major effort to establish and foster the use of a comprehensive set of internationally agreed safety standards for nuclear power plants. New initiatives are in progress to intensify international co-operative safety efforts through the exchange of information on safety-related operating occurrences, and through a more open sharing of safety research results. Emergency accident assistance lends itself to international co-operation and steps are being taken to establish an emergency assistance programme so the Agency can aid in co-ordinating a timely response to provide, at short notice, help and advice in case of a nuclear power accident. There has been some strengthening of those advisory services which involve missions of international experts primarily to countries with less developed nuclear power programmes, and in conjunction with the Technical Assistance Programme there is a co-ordinated programme for developing countries, involving safety training courses and assistance aimed at promoting an effective national regulatory programme in all countries using nuclear power. This paper discusses the major features of the IAEA activities in nuclear power plant safety. An understanding of the programme and its limitations is essential to its more effective use. Additional initiatives may still be proposed, but the possibilities for international and regional co-operation to assure an adequate level of safety world-wide already exist. (author)

  4. PUREX Deactivation Health and Safety documentation

    International Nuclear Information System (INIS)

    Dodd, E.N. III.

    1995-01-01

    The purpose of the PUREX Deactivation Project is to establish a passively safe and environmentally secure configuration of PUREX at the Hanford Site, and to preserve that configuration for a 10-year horizon. The 10-year horizon is used to predict future maintenance requirements and represents they typical time duration expended to define, authorize, and initiate the follow-on Decontamination and Decommissioning (D ampersand D) activities. This document was prepared to increase attention to worker safety issues during the deactivation project and, as such, identifies the documentation and programs associated with PUREX Deactivation Health and Safety

  5. The natural lifespan of a safety policy: violations and system migration in anaesthesia.

    Science.gov (United States)

    de Saint Maurice, Guillaume; Auroy, Yves; Vincent, Charles; Amalberti, René

    2010-08-01

    Safety rules continue growing rapidly, as if constraining human behaviour was the unique avenue for reaching ultimate safety. Safety rules are essential for a safe system, but their multiplication can have counterproductive effects. To monitor, in an anaesthesia ward, compliance with a process-oriented safety rule, and understand barriers and facilitators which help and hinder physicians from following guidelines. The rule stipulated that the day before surgery anaesthetists had to record in the patient's file the drugs to be used for the anaesthesia (induction, maintenance, airway control). Compliance was assessed before introduction of the rule, immediately after, at 6 months and at 12 months. All medical staff were blinded to the protocol. 717 patient records were included. The results showed an initial compliance with policy, reaching 86% for some items (never 100%). Reduction began within 6 months and returned almost to initial levels within a year. One individual showed poor compliance throughout the study but even initially compliant doctors experienced a reduction. Compliance was higher for complex surgery but lower for unscheduled surgery and when job pressure was greater. Compliance eroded over time. A major trigger of erosion seemed to be lack of continued compliance by a senior member of staff. Rules and procedures constitute fragile safety barriers, and it may be better to forego introducing a new safety rule if it is not considered as a priority by staff and is therefore vulnerable to sacrifice in case of conflict with competitive demands.

  6. Assessing and improving the safety culture of non-power nuclear installations

    International Nuclear Information System (INIS)

    Bastin, S.J.; Cameron, R.F.; McDonald, N.R.; Adams, A.; Williamson, A.

    2000-01-01

    The development and application of safety culture principles has understandably focused on nuclear power plant and fuel cycle facilities and has been based on studies in Europe, North America, Japan and Korea. However, most radiation injuries and deaths have resulted from the mishandling of radioactive sources, inadvertent over-exposure to X-rays and critically incidents, unrelated to nuclear power plant. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has been promoting initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. ANSTO initiated a Safety Culture Project in 1996 to develop methods for assessing and improving safety culture at nuclear and radiation installations other than power reactors and to trial these at ANSTO and in the Asian region. The project has sensibly drawn on experience from the nuclear power industry, particularly in Japan and Korea. There has been a positive response in the participating countries to addressing safety culture issues in non-power nuclear facilities. This paper reports on the main achievements of the project. Further goals of the project are also identified. (author)

  7. Physicochemical, nutritive and safety evaluation of local cereal ...

    African Journals Online (AJOL)

    SARAH

    2014-11-30

    Nov 30, 2014 ... practices and good manufacturing processing should be considered. Such initiatives need to be carried amongst local cereal producers to help minimize food safety risk and ... potential for contamination and deterioration with.

  8. Innovation and Safety. A prestudy

    International Nuclear Information System (INIS)

    Rollenhagen, Carl; Hansson, Sven Ove; Hortberg, Johan; Jakobsson, Fredrik; Zhau, Victoria Jing; Mojeri, Sara

    2010-04-01

    The project summarized in this report was initiated to explore relations between innovation and safety. The first two sections of the report discuss some previously conducted research and give a general background to the subject. It is concluded that safety research and innovation research, by and large, has developed as separate academic disciplines. The concepts of 'innovative safety culture' and 'safe innovation cultures' are suggested as two concepts that can be used to integrate research: innovative safety cultures depart from safety culture research but attempts to introduce an innovative dimension with the aim to create adaptive and innovative safety cultures that efficiently can handle risks arising from existing innovations. Safe innovation cultures have focus on innovation itself, but with the ambition to introduce concepts and methods from safety research in the innovative processes. Three subprojects conducted in the context of the present research are summarized. The first project examines how an existing organization (e.g. SKB - Swedish Nuclear Fuel and Waste Management) attempts to integrate both innovative activities and operative activities in the same organisation. Interviews with key personnel explored different views about how innovative and safety work coexists in the organisation. The second project focuses on how major retrofit projects of a nuclear power plant is managed in parallel to operative activities (e.g. operating the plant on an everyday basis). By means of an innovative technique (e.g. system groups) seminars were held to suggest improvements in the technical change process. The third project conducted a risk analysis of a major organisational change (e.g. control centres for energy distribution). Experiences from the three projects are finally discussed in terms of similarities and differences associated with the cultures for innovation and safety. Suggestions for further research are made

  9. The dual effects of leading for safety: The mediating role of employee regulatory focus.

    Science.gov (United States)

    Kark, Ronit; Katz-Navon, Tal; Delegach, Marianna

    2015-09-01

    This study examined the underlying mechanisms through which transformational and transactional leadership influence employee safety behaviors. Linking leadership theory with self-regulatory focus (SRF) theory, we examined a model of dual effects of leadership on safety initiative and safety compliance behaviors as mediated by promotion and prevention self-regulations. We conducted an experimental study (N = 107), an online study (N = 99) and a field study (N = 798 employees and 49 managers). Results demonstrated that followers' situational promotion focus mediated the positive relationship between transformational leadership and safety initiative behaviors. Through all 3 studies, transactional active leadership was positively associated with followers' situational prevention focus, however, the association between followers' prevention focus and safety compliance behaviors was inconsistent, showing the expected mediation relationships in the experimental setting, but not in the online and field studies. We discuss theoretical and practical implications of the findings. (c) 2015 APA, all rights reserved).

  10. Development of ABWR-2 and its safety design

    International Nuclear Information System (INIS)

    Takafumi, Anegawa; Kenji, Tateiwa

    2002-01-01

    This paper reports the current status of development project on ABWR-II, a next generation reactor design based on ABWR, and its safety design. This project was initiated over a decade ago and has completed three phases to date. In Phase I (1991-92), basic design requirements were discussed and several plant concepts were studied. In Phase II (1993-95), key design features were selected in order to establish a reference reactor concept. In Phase III (1996-2000), based on the reference reactor concept, modifications and improvements were made to fulfill the design requirements. By adopting large electric output (1 700 MW), large fuel bundle, modified ECCS, and passive heat removal systems, among other design features, we achieved a design concept capable of increasing both economic competitiveness and safety performance. Main focus of this paper will be on the safety design, safety performance, and further research needs related to safety. (authors)

  11. The complexity of patient safety reporting systems in UK dentistry.

    Science.gov (United States)

    Renton, T; Master, S

    2016-10-21

    Since the 'Francis Report', UK regulation focusing on patient safety has significantly changed. Healthcare workers are increasingly involved in NHS England patient safety initiatives aimed at improving reporting and learning from patient safety incidents (PSIs). Unfortunately, dentistry remains 'isolated' from these main events and continues to have a poor record for reporting and learning from PSIs and other events, thus limiting improvement of patient safety in dentistry. The reasons for this situation are complex.This paper provides a review of the complexities of the existing systems and procedures in relation to patient safety in dentistry. It highlights the conflicting advice which is available and which further complicates an overly burdensome process. Recommendations are made to address these problems with systems and procedures supporting patient safety development in dentistry.

  12. Development of a safety parameter supervision system for Angra-1

    International Nuclear Information System (INIS)

    Silva, R.A. da; Thome Filho, Z.D.; Schirru, R.; Martinez, A.S.; Oliveira, L.F.S. de

    1986-01-01

    The Safety Parameter Supervision System (SSPS) which is a computerized system for monitoring essential parameters in real time, determining the safety status and emergency procedures for returning normal reactor operation, in case of an anomaly occurrence, is presented. The SSPS consists of three sub-systems: Integrated parameter monitoring system which gives to operators an integrated vision of values of a parameter set, able to detect any deviation of normal reactor operation; safety critical function system which evaluates safety status in terms of a safety critical function set appointed in advance, and in case of violation of any critical function, it initiates the adequate emergency procedure to return normal operation; and safety parameter computer system which carries out the arquirement of analogic and digital control signals of nuclear power plant. (M.C.K.) [pt

  13. Contribution of operating feedback to probabilistic safety studies

    International Nuclear Information System (INIS)

    Guio, J.M. de; Lannoy, A.

    1992-03-01

    This paper presents the method used for PWR unit operation feedback analysis and its contribution to probabilistic safety studies. The targets were as follows: - use of failure data banks to assess reliability parameters, - use of event data banks to identify and quantify main system initiating events, - determination of a standard operating profile. These studies, performed in the context of nuclear power plant safety programs, prove useful not only to safety engineers but also to equipment experts, designers, operators and maintenance specialists. They constitute basic data for studies in all these areas or the departure point for new investigations. (authors). 3 figs., 3 tabs., 3 refs

  14. Nuclear safety review for the year 2001

    International Nuclear Information System (INIS)

    2002-07-01

    The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

  15. Towards a Competency-based Vision for Construction Safety Education

    Science.gov (United States)

    Pedro, Akeem; Hai Chien, Pham; Park, Chan Sik

    2018-04-01

    Accidents still prevail in the construction industry, resulting in injuries and fatalities all over the world. Educational programs in construction should deliver safety knowledge and skills to students who will become responsible for ensuring safe construction work environments in the future. However, there is a gap between the competencies current pedagogical approaches target, and those required for safety in practice. This study contributes to addressing this issue in three steps. Firstly, a vision for competency-based construction safety education is conceived. Building upon this, a research scheme to achieve the vision is developed, and the first step of the scheme is initiated in this study. The critical competencies required for safety education are investigated through analyses of literature, and confirmed through surveys with construction and safety management professionals. Results from the study would be useful in establishing and orienting education programs towards current industry safety needs and requirements

  16. Introduction to 'International Handbook of Criticality Safety Benchmark Experiments'

    International Nuclear Information System (INIS)

    Komuro, Yuichi

    1998-01-01

    The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization for Economic Cooperation and Development-Nuclear Energy Agency (OECD-NEA). 'International Handbook of Criticality Safety Benchmark Experiments' was prepared and is updated year by year by the working group of the project. This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used. The author briefly introduces the informative handbook and would like to encourage Japanese engineers who are in charge of nuclear criticality safety to use the handbook. (author)

  17. Safety aspects in radiology

    International Nuclear Information System (INIS)

    Silva, D.C. da.

    1991-05-01

    The development of a program for the evaluation of the physical installations and operational procedures in diagnostic radiology with respect to radiation-safety is described. In addition, a proposal for the quality analysis of X-ray equipment and film-processing is presented. The purpose is both to ensure quality and safety of the radiology service, as well as to aid in the initial and in-service training of the staff. Interviews with patients, staff practicing radiology at a wide range of levels and the controlling authorities were carried out in the State of Rio de Janeiro in order to investigate the existence and the effective use of personal radioprotection equipment as well as user's and staff's concern for radiation safety. Additionally physical measurements were carried out in University Hospitals in Rio de Janeiro to assess the quality of equipment in day-to-day use. It was found that in the locations which did not have routine maintenance the equipment was generally in a poor state which lead to a high incidence of repetition of examinations and the consequent financial loss. (author)

  18. Safety culture competition - expectations of a regulatory authority

    International Nuclear Information System (INIS)

    Keil, D.; Gloeckle, W.

    2000-01-01

    The accident at the Chernobyl nuclear power station on April 26, 1986 influenced the development of reactor safety and promulgated two basic concepts especially in Germany. On the one hand, extensive measures of in-plant accident management have greatly reduced the so-called residual risk. On the other hand, a comprehensive safety approach has been initiated which comprises the nuclear power plant as a system together with people, technology, and organization and also includes safety culture. In a modern regulatory concept based on the dynamic development of safety, the authority's classical regulatory function of controlling is supplemented by the objective of promoting safety. While preserving the division of responsibilities between the regulatory authority and plant operators, the authority uses 'constructive critical dialog' as a tool to enhance safety. Besides the regulatory assessment of safety culture on the basis of indications or indicators, also the continuous promotion of safety culture in a dialog with plant operators is seen as one of the duties of a regulatory authority. Continued efforts are necessary to maintain the high level of safety culture in German nuclear power plants. Operators are expected to establish a safety management which assigns top priority to safety issues, and which pursues the goal of supervising and promoting safety culture. Developments on the deregulated electricity markets must not lead to safety aspects ranking second to economic aspects. Moreover, also under changed boundary conditions, only the safe operation of nuclear power plants ensures economic viability. (orig.) [de

  19. Trust-based approaches to safety and production

    NARCIS (Netherlands)

    Conchie, Stacey M.; Woodcock, Helena E.; Taylor, Paul J.; Clarke, Sharon; Probst, Tahira M.; Guldenmund, Frank; Passmore, Jonathan

    2015-01-01

    This chapter discusses the importance of interpersonal trust in the creation of a safe work environment. It highlights that trust is important in increasing employee engagement in safety, willingness to comply with management requests, and propensity to take the initiative. The chapter commences

  20. International Nuclear Safety Center (INSC) database

    International Nuclear Information System (INIS)

    Sofu, T.; Ley, H.; Turski, R.B.

    1997-01-01

    As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

  1. John M. Eisenberg Patient Safety Awards. System innovation: Veterans Health Administration National Center for Patient Safety.

    Science.gov (United States)

    Heget, Jeffrey R; Bagian, James P; Lee, Caryl Z; Gosbee, John W

    2002-12-01

    In 1998 the Veterans Health Administration (VHA) created the National Center for Patient Safety (NCPS) to lead the effort to reduce adverse events and close calls systemwide. NCPS's aim is to foster a culture of safety in the Department of Veterans Affairs (VA) by developing and providing patient safety programs and delivering standardized tools, methods, and initiatives to the 163 VA facilities. To create a system-oriented approach to patient safety, NCPS looked for models in fields such as aviation, nuclear power, human factors, and safety engineering. Core concepts included a non-punitive approach to patient safety activities that emphasizes systems-based learning, the active seeking out of close calls, which are viewed as opportunities for learning and investigation, and the use of interdisciplinary teams to investigate close calls and adverse events through a root cause analysis (RCA) process. Participation by VA facilities and networks was voluntary. NCPS has always aimed to develop a program that would be applicable both within the VA and beyond. NCPS's full patient safety program was tested and implemented throughout the VA system from November 1999 to August 2000. Program components included an RCA system for use by caregivers at the front line, a system for the aggregate review of RCA results, information systems software, alerts and advisories, and cognitive acids. Following program implementation, NCPS saw a 900-fold increase in reporting of close calls of high-priority events, reflecting the level of commitment to the program by VHA leaders and staff.

  2. Making safety an integral part of 5S in healthcare.

    Science.gov (United States)

    Ikuma, Laura H; Nahmens, Isabelina

    2014-01-01

    Healthcare faces major challenges with provider safety and rising costs, and many organizations are using Lean to instigate change. One Lean tool, 5S, is becoming popular for improving efficiency of physical work environments, and it can also improve safety. This paper demonstrates that safety is an integral part of 5S by examining five specific 5S events in acute care facilities. We provide two arguments for how safety is linked to 5S:1. Safety is affected by 5S events, regardless of whether safety is a specific goal and 2. Safety can and should permeate all five S's as part of a comprehensive plan for system improvement. Reports of 5S events from five departments in one health system were used to evaluate how changes made at each step of the 5S impacted safety. Safety was affected positively in each step of the 5S through initial safety goals and side effects of other changes. The case studies show that 5S can be a mechanism for improving safety. Practitioners may reap additional safety benefits by incorporating safety into 5S events through a safety analysis before the 5S, safety goals and considerations during the 5S, and follow-up safety analysis.

  3. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  4. The in-depth safety assessment (ISA) pilot projects in Ukraine

    International Nuclear Information System (INIS)

    Kot, C. A.

    1998-01-01

    Ukraine operates pressurized water reactors of the Soviet-designed type, VVER. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs). After approval of the SARS by the Ukrainian Nuclear Regulatory Authority, the plants will be granted longer-term operating licenses. In September 1995, the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine issued a new contents requirement for the safety analysis reports of VVERs in Ukraine. It contains requirements in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The DBA requirements are an expanded version of the older SAR requirements. The last two requirements, on PRA and BDBA, are new. The US Department of Energy (USDOE), through the International Nuclear Safety Program (INSP), has initiated an assistance and technology transfer program to Ukraine to assist their nuclear power stations in developing a Western-type technical basis for the new SARS. USDOE sponsored In-Depth Safety Assessments (ISAs) have been initiated at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1. USDOE/INSP have structured the ISA program in such a way as to provide maximum assistance and technology transfer to Ukraine while encouraging and supporting the Ukrainian plants to take the responsibility and initiative and to perform the required assessments

  5. Systematic evaluation program. Status report and initial evaluation

    International Nuclear Information System (INIS)

    1983-06-01

    The MHB Ongoing Systematic Evaluation Program (SEP) Assessment Study was initiated by the Swedish Nuclear Power Inspectorate (SKI) in 1980. This MHB report is a status report and initial evaluation of SEP. The methodology and results of SEP are disscused with particular emphasis on the first two SEP plant reviews - the Palisades and R.E. Ginna nuclear power plants. The comments of cognizant persons in the NRC and the ACRS, as well as private consultants, are included herein. MHBs major findings are as follows: The SEP plant review methodology was acceptable to the NRC Commissioners, the ACRS, and the NRC Staffs consultants who evaluated the first two SEP plant reviews. A concern raised by all who commented on SEP was the absence of Three Mile Island Action Plan Items and Unresolved Safety Issues from current SEP reviews. The SEP reviews of the Palisades and R.E. Ginna plants concluded that the two plant designs were adequate with respect to a majority of safety topics. Several topics remain unresolved in both the Palisades and R.E. Ginna SEP reviews. In the case of the Ginna plant, several related topics have been grouped together in a major structural reevaluation study. In general, due to the number of unresolved and excluded topics, SEP has not at this time produced a plant safety evaluation which can be considered complete and integrated. (author)

  6. Integrated care: an Information Model for Patient Safety and Vigilance Reporting Systems.

    Science.gov (United States)

    Rodrigues, Jean-Marie; Schulz, Stefan; Souvignet, Julien

    2015-01-01

    Quality management information systems for safety as a whole or for specific vigilances share the same information types but are not interoperable. An international initiative tries to develop an integrated information model for patient safety and vigilance reporting to support a global approach of heath care quality.

  7. Nuclear Safety. 1997; Surete Nucleaire. 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-19

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  8. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

    International Nuclear Information System (INIS)

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  9. Environmental Regulation and Food Safety: Studies of Protection ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    2006-01-01

    Jan 1, 2006 ... Book cover Environmental Regulation and Food Safety: Studies of ... are sometimes perceived in developing countries as nontariff barriers to trade. ... In some cases, products that had initially been refused access to a ...

  10. PROPOSAL OF VOIVODESHIP ROAD SAFETY IMPROVEMENT PROGRAMME

    Directory of Open Access Journals (Sweden)

    Tomasz SZCZURASZEK

    2016-07-01

    Full Text Available The article presents a proposal of the ‘GAMBIT KUJAWSKO-POMORSKI’ Road Safety Improvement Programme. The main idea of the Programme is to establish and initiate systems that will be responsible for the most important areas of activity within road safety, including road safety control, supervision, and management systems in the whole Voivodeship. In total, the creation and start of nine such systems has been proposed, namely: the Road Safety Management, the Integrated Road Rescue Service, the Personnel Continuing Education, the Hazardous Road Behaviour Monitoring, the Social Education for Safe Behaviour on Road, the Teaching Personnel Improvement, the Area Development and Planning Process Improvement, the Road Infrastructure Design Quality Improvement, and the Road and Traffic Management Process Efficiency Improvement. The basic aim of each system has been discussed as well as the most important tasks implemented as its part. The Road Safety Improvement Programme for the Kujawsko-Pomorskie Voivodeship presented in this article is a part of the National Road Safety Programme 2013-2020. Moreover, it is not only an original programme in Poland, but also a universal project that may be adapted for other voivodeships as well.

  11. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  12. The emphasis is on reactor safety research

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    For the second time the Association for Reactor Safety mbH (GRS), Koeln, organised on behalf of the BMFT the conference 'Reactor safety research'. About 400 visitors took part. The public who were interested were given a review of the activities which are being undertaken by the BMFT in the programme 'Research and safety of light-water reactors'. The series of conference papers initiated by the BMFT is to be developed into a permanent information source which will be of interest to those working on nuclear questions such as official quarters, industry and high schools, and experts who have to give judgements. The most important statements by various research groups in industry, high schools and also associations of experts, are summarised. (orig.) [de

  13. Glue Guns: Aiming for Safety

    Science.gov (United States)

    Roy, Ken

    2010-01-01

    While glue guns are very useful, there are safety issues. Regardless of the temperature setting, glue guns can burn skin. The teacher should demonstrate and supervise the use of glue guns and have a plan should a student get burned. There should be an initial first aid protocol in place, followed by a visit to the school nurse. An accident report…

  14. Nuclear medicine software: safety aspects

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    A brief editorial discusses the safety aspects of nuclear medicine software. Topics covered include some specific features which should be incorporated into a well-written piece of software, some specific points regarding software testing and legal liability if inappropriate medical treatment was initiated as a result of information derived from a piece of clinical apparatus incorporating a malfunctioning computer program. (U.K.)

  15. Complementary assessment of the safety of French nuclear power plants

    International Nuclear Information System (INIS)

    Camarcat, N.; Pouget-Abadie, X.

    2011-01-01

    As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

  16. National Partnership for Maternal Safety: Consensus Bundle on Obstetric Hemorrhage.

    Science.gov (United States)

    Main, Elliott K; Goffman, Dena; Scavone, Barbara M; Low, Lisa Kane; Bingham, Debra; Fontaine, Patricia L; Gorlin, Jed B; Lagrew, David C; Levy, Barbara S

    2015-07-01

    Hemorrhage is the most frequent cause of severe maternal morbidity and preventable maternal mortality and therefore is an ideal topic for the initial national maternity patient safety bundle. These safety bundles outline critical clinical practices that should be implemented in every maternity unit. They are developed by multidisciplinary work groups of the National Partnership for Maternal Safety under the guidance of the Council on Patient Safety in Women's Health Care. The safety bundle is organized into four domains: Readiness, Recognition and Prevention, Response, and Reporting and System Learning. Although the bundle components may be adapted to meet the resources available in individual facilities, standardization within an institution is strongly encouraged. References contain sample resources and "Potential Best Practices" to assist with implementation.

  17. Design, production and initial state of the backfill and plug in deposition tunnels

    Energy Technology Data Exchange (ETDEWEB)

    Boerjesson, Lennart; Gunnarsson, David; Johannesson, Lars-Erik; Jonsson, Esther

    2010-12-15

    The report is included in a set of Production reports, presenting how the KBS-3 repository is designed, produced and inspected. The set of reports is included in the safety report for the KBS-3 repository and repository facility. The report provides input on the initial state of the backfill and plug in deposition tunnels for the assessment of the long-term safety, SR-Site. The initial state refers to the properties of the engineered barriers once they have been finally placed in the KBS-3 repository and will not be further handled within the repository facility. In addition, the report provides input to the operational safety report, SR-Operation, on how the backfill and plug shall be handled and installed. The report presents the design premises and reference designs of the backfill and plug in deposition tunnels and verifies their conformity to the design premises. It also describes the production of the backfill from excavation and delivery of backfill material to installation in the deposition tunnel, and gives an outline of the installation of the plug. Finally, the initial states of the backfill and plug and their conformity to the reference designs and design premises are presented

  18. Analysing supercritical water reactor's (SCWR's) special safety systems using probabilistic tools

    International Nuclear Information System (INIS)

    Ituen, I.; Novog, D.R.

    2011-01-01

    The next generation of reactors, termed Generation IV, has very attractive features -- its superior safety characteristics, high thermal efficiency, and fuel cycle sustainability. A key element of the Generation IV designs is the improvement in safety, which in turn requires improvements in safety system performance and reliability, as well as a reduction in initiating event frequencies. This study compares the response of the systems important to safety in the CANDU-Supercritical Water Reactor to those of the generic CANDU under a main steamline break accident and loss of forced circulation events -- to quantify the improvements in safety for the pre-conceptual CANDU SCWR design. Probabilistic safety analysis is the tool used in this study to test the behavior of the pre- conceptual design during these events. (author)

  19. Safety engineering experiments of explosives

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, Noboru

    1987-07-24

    The outline of large scale experiments carried out every year since 1969 to obtain fundamental data and then establish the safety engineering standards concerning the manufacturing, storage and transportation, etc. of all explosives was described. Because it becomes recently difficult to ensure the safety distance in powder magazines and powder plants, the sandwich structure with sand is thought to be suitable as the neighboring barrier walls. The special vertical structure for embankments to provide against a emergency explosion is effective to absorb the blast. Explosion behaviors such as initiating sensitivity, detonation, sympathetic detonation, and shock occurence of the ANFO explosives in place of dynamite and the slurry explosives were studied. The safety engineering standards for the manufacturing and application of explosives were studied to establish because accidents by tabacco fire are not still distinguished. Much data concerning early stage fire fighting, a large quantity of flooding and shock occurence from a assumption of ignition during machining in the propellants manufacturing plant, could be obtained. Basic studies were made to prevent pollution in blasting sites. Collected data are utilized for the safety administration after sufficient discussion. (4 figs, 2 tabs, 3 photos, 17 refs)

  20. Measuring and managing safety at Wahleach Dam

    International Nuclear Information System (INIS)

    Salmon, G. M.; Cattanach, J. D.; Hartford, D. N. D.

    1996-01-01

    Safety improvements recently implemented at the Wahleach Dam were described as one of the first instances in international dam safety practice where risk concepts have been used in conjunction with acceptable risk criteria to evaluate safety of a dam relative to required level of safety. Erosion was identified as the greatest threat to the safety of the dam. In addressing the deficiencies B.C. Hydro formulated a process which advocates a balanced level of safety,i.e. the probability of failure multiplied by the consequences of failure, integrated over a range of initiators. If the risk posed by the dam is lower than a 'tolerable' risk, the dam is considered to be safe enough. In the case of the Wahleach Dam, the inflow design flood (IDF) was selected to be about one half of the probable maximum flow (PMF), hence it was more likely than not that the spillway could pass floods up to and including the PMF. By accepting the determined level of risk, expenditures of several million dollars for design and construction of dam safety improvements were made redundant. Another byproduct of this new concept of risk assessment was the establishment of improved life safety protection by means of an early warning system for severe floods through the downstream community and emergency authorities. 3 refs., 5 tabs

  1. Post Chernobyl safety review at Ontario Hydro

    International Nuclear Information System (INIS)

    Frescura, G.M.; Luxat, J.C.; Jobe, C.

    1991-01-01

    It is generally recognized that the Chernobyl Unit 4 accident did not reveal any new phenomena which had not been previously identified in safety analyses. However, the accident provided a tragic reminder of the potential consequences of reactivity initiated accidents (RIAs) and stimulated nuclear plant operators to review their safety analyses, operating procedures and various operational and management aspects of nuclear safety. Concerning Ontario Hydro, the review of the accident performed by the corporate body responsible for nuclear safety policy and by the Atomic Energy Control Board (the Regulatory Body) led to a number of specific recommendations for further action by various design, analysis and operation groups. These recommendations are very comprehensive in terms of reactor safety issues considered. The general conclusion of the various studies carried out in response to the recommendations, is that the CANDU safety design and the procedures in place to identify and mitigate the consequences of accidents are adequate. Improvements to the reliability of the Pickering NGSA shutdown system and to some aspects of safety management and staff training, although not essential, are possible and would be pursued. In support of this conclusion, the paper describes some of the studies that were carried out and discusses the findings. The first part of the paper deals with safety design aspects. While the second is concerned with operational aspects

  2. Preliminary safety information document for the standard MHTGR. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-01-01

    This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

  3. Requirements on the provisional safety analyses and technical comparison of safety measures

    International Nuclear Information System (INIS)

    2010-04-01

    The concept of a Geological Underground Repository (SGT) was adopted by the Swiss Federal Council on April 2 nd , 2008. It fixes the goals and the safety technical criteria as well as the procedures for the choice of the site for an underground repository. Those responsible for waste management evaluate possible site regions according to the present status of geological knowledge and based on the safety criteria defined in SGT as well as on technical feasibility. In a first step, they propose geological repository sites for high level (HAA) and for low and intermediate level (SMA) radioactive wastes and justify their choice in a report delivered to the Swiss Federal Office of Energy. The Swiss Federal Council reviews the choices presented and, in the case of positive evaluation, approves them and considers them as an initial orientation. In a second step, based on the possible sites according to step 1, the waste management institution responsible has to reduce the repositories chosen for HAA and SMA by taking into account safety aspects, technical feasibility as well as space planning and socio-economical aspects. In making this choice, safety aspects have the highest priority. The criteria used for the evaluation in the first step have to be defined using provisional quantitative safety analyses. On the basis of the whole appraisal, including space planning and socio-economical aspects, those responsible for waste management propose at least two repository sites for HAA- and SMA-waste. Their selection is then reviewed by the authorities and, in the case of a positive assesment, the selection is taken as an intermediate result. The remaining sites are further studied to examine site choice and the delivery of a request for a design license. If necessary, the requested geological knowledge has to be confirmed by new investigations. Based on the results of the choosing process and a positive evaluation by the safety authorities, the Swiss Federal Council has to

  4. 75 FR 75707 - Request for Public Comment on the Draft National Nanotechnology Initiative Strategy for...

    Science.gov (United States)

    2010-12-06

    ... Nanotechnology Initiative Strategy for Nanotechnology-Related Environmental, Health, and Safety Research AGENCY..., Engineering, and Technology Subcommittee of the National Science and Technology Council request comments from the public regarding the draft National Nanotechnology Initiative (NNI) Strategy for Nanotechnology...

  5. 76 FR 2428 - Request for Public Comment on the Draft National Nanotechnology Initiative Strategy for...

    Science.gov (United States)

    2011-01-13

    ... Nanotechnology Initiative Strategy for Nanotechnology-Related Environmental, Health, and Safety Research AGENCY..., Engineering, and Technology Subcommittee of the National Science and Technology Council request comments from the public regarding the draft National Nanotechnology Initiative (NNI) Strategy for Nanotechnology...

  6. Navigating School Safety Law and Policy

    Science.gov (United States)

    Vaillancourt, Kelly; Rossen, Eric

    2012-01-01

    Initiatives designed to improve school safety and conditions for learning have become central to education reform efforts at the local, state, and national levels. These efforts often target the reduction and prevention of bullying, discrimination, and harassment in schools. While most states currently have some form of law or policy designed to…

  7. Summary of LWR safety research in the USA

    International Nuclear Information System (INIS)

    Murley, T.E.; Tong, L.S.; Bennett, G.L.

    1977-01-01

    The U.S. Nuclear Regulatory Commission's water reactor safety research program is described and the basic results are presented. The USNRC water reactor safety research program consists of five basic research areas: integrity of vessel and piping, thermal-hydraulic test, fuel rod behaviour, code development and verification, and reactor operational safety. Results from the vessel and piping integrity research have demonstrated the high safety margins in scaled vessels and the analytical procedures for calculating vessel behaviour under pressure. Non-destructive examination techniques are being improved. Work is also proceeding to define the material constituents to reduce the susceptibility of irradiation embrittlement and stress corrosion cracking. The thermal-hydraulic tests have covered the various phases of a hypothetical loss of coolant accident (LOCA) and activation of the emergency core cooling system (ECCS). These tests have led to the development of engineering correlations to describe the phenomena to further quantify the safety margins in commercial nuclear power plants. Specifically, this paper presents selected experimental data and analytical predictions from the initial tests in LOFT and SEMISCALE. Comparisons and evaluations are made between the data and analytical predictions. Significant results and conclusions are presented regarding the behaviour of emergency core cooling systems in a LOCA environment: the ability to predict LOCA-type experiments over a scaling range of thirty and the thermal-hydraulic behaviour of components such as pumps in an integral system LOCA environment. The fuel behaviour research has provided valuable information on decay heat, cladding oxidation, fuel rod behaviour and fuel metling. Both the decay heat and the cladding oxidation have been shown to be lower than assumed in the licensing evaluations. The fuel behaviour and thermo-hydraulic research is being integrated into computer codes to be used to provide additional

  8. Fusion Safety Program annual report, fiscal year 1992

    International Nuclear Information System (INIS)

    Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

    1993-01-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

  9. Fusion Safety Program annual report: Fiscal year 1987

    International Nuclear Information System (INIS)

    Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

    1988-02-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

  10. On-going and some future safety related activities of the OECD/NEA

    International Nuclear Information System (INIS)

    Frescura, G.

    2001-01-01

    The CSNI and CNRA structures and current activities of direct relevance to WWERs are presented. The nuclear regulatory challenges arising from economic deregulation like: direct safety challenges, infrastructure issues, increased pressure on regulatory bodies etc. are given. The OECD/NEA initiatives on assuring nuclear safety competence are mentioned

  11. Application of a model for delivering occupational safety and health to smaller businesses: Case studies from the US

    Science.gov (United States)

    Cunningham, Thomas R.; Sinclair, Raymond

    2015-01-01

    Smaller firms are the majority in every industry in the US, and they endure a greater burden of occupational injuries, illnesses, and fatalities than larger firms. Smaller firms often lack the necessary resources for effective occupational safety and health activities, and many require external assistance with safety and health programming. Based on previous work by researchers in Europe and New Zealand, NIOSH researchers developed for occupational safety and health intervention in small businesses. This model was evaluated with several intermediary organizations. Four case studies which describe efforts to reach small businesses with occupational safety and health assistance include the following: trenching safety training for construction, basic compliance and hazard recognition for general industry, expanded safety and health training for restaurants, and fall prevention and respirator training for boat repair contractors. Successful efforts included participation by the initiator among the intermediaries’ planning activities, alignment of small business needs with intermediary offerings, continued monitoring of intermediary activities by the initiator, and strong leadership for occupational safety and health among intermediaries. Common challenges were a lack of resources among intermediaries, lack of opportunities for in-person meetings between intermediaries and the initiator, and balancing the exchanges in the initiator–intermediary–small business relationships. The model offers some encouragement that initiator organizations can contribute to sustainable OSH assistance for small firms, but they must depend on intermediaries who have compatible interests in smaller businesses and they must work to understand the small business social system. PMID:26300585

  12. Fusion Safety Program annual report: Fiscal year 1986

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-06-01

    This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

  13. Safety of reactors built according to earlier standards (WWER 440/V230 type)

    International Nuclear Information System (INIS)

    Misak, J.; Rohar, S.

    1995-01-01

    The problems of safety of WWER-440/V-230 type reactors are discussed, and the following conclusions are made. (1) The reactors have a very good operational record. (2) The reactors have serious design shortcomings, which should be eliminated by safety upgrading. Core damage frequency should be further reduced. (3) PSA methods constitute an appropriate tool for assessment of plant vulnerability to some initiating events and malfunctions, for prioritization of upgrading measures and for tolerability of deviations from current safety standards. (4) The most important safety merits, such as a large thermal inertia and low rupture probability, should be properly taken into account in the analysis. (5) Extensive safety upgrading is feasible and can lead to a considerable risk reduction. In certain circumstances such upgrading is the least expensive option even though the total cost is much higher than the initial plant construction cost. (6) Properly upgraded, the reactor units may be operable until better power resources are available within the country. (7) The existing gap between the technological and political judgements of nuclear safety should be reduced continuously by information exchange improvements. (8) A unified approach to nuclear safety should be adopted for all nuclear reactors (not just WWERs) built to earlier standards. 5 tabs., 1 fig

  14. Results of the CANDU 3 probabilistic safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jaitly, R K [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada)

    1996-12-31

    The purpose of the Conceptual Probabilistic Safety Assessment (PSA) of the CANDU 3 reactor was to provide safety assistance in the early stages of design to ensure that the design included adequate redundancy and functional separation of the mitigating systems; the final design should therefore give better results, particularly after modifications involving control, electrical power, instrument air, and service water. The initial PSA gave a total CANDU 3 core damage frequency of 7.8 x 10{sup -6}/year. 4 refs., 1 fig.

  15. Results of the CANDU 3 probabilistic safety assessment

    International Nuclear Information System (INIS)

    Jaitly, R.K.

    1995-01-01

    The purpose of the Conceptual Probabilistic Safety Assessment (PSA) of the CANDU 3 reactor was to provide safety assistance in the early stages of design to ensure that the design included adequate redundancy and functional separation of the mitigating systems; the final design should therefore give better results, particularly after modifications involving control, electrical power, instrument air, and service water. The initial PSA gave a total CANDU 3 core damage frequency of 7.8 x 10 -6 /year. 4 refs., 1 fig

  16. The Nordic programme for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    1992-02-01

    The description of planned projects concerning nuclear safety is divided under the headings of readiness for action in situations of abnormal radiation, nuclear wastes and deposition, radioecology, and reactor safety - professional emergency-readiness. Coordination initiatives are also dealt with. In addition to this a survey of projects, coordinators and project leaders and a description of suggested new measures for nuclear safety are given. Under the first heading the subjects dealt with are spreading and local consequences, strategies, measuring methods and data exchange and management for decision-makers, evaluation, harmonization and effecting of plans, public information, a nordic emergency action exercise and reduction data connected with contaminated areas. The second heading covers criteria for classification of radioactive material, experiences in demolition of uranium-cleaning plants, information management, waste management in the case of field deposition with radioactivity from past reactor accidents and climatological and geological processes of significance for long-duration safety. Subjects under the third heading of radioecology cover training, quality assurance, aquatic radioecology, agricultural and natural ecosystems. Subjects under reactor safety include safety evaluation, the course of serious accidents, and data on neighbour-reactor system's conditions of safety. (AB)

  17. Environment, safety and health progress assessment manual

    International Nuclear Information System (INIS)

    1992-12-01

    On June 27, 1989, the Secretary of Energy announced a 1O-Point Initiative to strengthen environment,safety, and health (ES ampersand H) programs, and waste management activities at involved conducting DOE production, research, and testing facilities. One of the points independent Tiger Team Assessments of DOE operating facilities. The Office of Special Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This volume contains appendices to the Environment, Safety and Health Progress Assessment Manual

  18. Characteristics of patients initiating raloxifene compared to those initiating bisphosphonates

    Directory of Open Access Journals (Sweden)

    Wang Sara

    2008-12-01

    Full Text Available Abstract Background Both raloxifene and bisphosphonates are indicated for the prevention and treatment of postmenopausal osteoporosis, however these medications have different efficacy and safety profiles. It is plausible that physicians would prescribe these agents to optimize the benefit/risk profile for individual patients. The objective of this study was to compare demographic and clinical characteristics of patients initiating raloxifene with those of patients initiating bisphosphonates for the prevention and treatment of osteoporosis. Methods This study was conducted using a retrospective cohort design. Female beneficiaries (45 years and older with at least one claim for raloxifene or a bisphosphonate in 2003 through 2005 and continuous enrollment in the previous 12 months and subsequent 6 months were identified using a collection of large national commercial, Medicare supplemental, and Medicaid administrative claims databases (MarketScan®. Patients were divided into two cohorts, a combined commercial/Medicare cohort and a Medicaid cohort. Within each cohort, characteristics (demographic, clinical, and resource utilization of patients initiating raloxifene were compared to those of patients initiating bisphosphonate therapy. Group comparisons were made using chi-square tests for proportions of categorical measures and Wilcoxon rank-sum tests for continuous variables. Logistic regression was used to simultaneously examine factors independently associated with initiation of raloxifene versus a bisphosphonate. Results Within both the commercial/Medicare and Medicaid cohorts, raloxifene patients were younger, had fewer comorbid conditions, and fewer pre-existing fractures than bisphosphonate patients. Raloxifene patients in both cohorts were less likely to have had a bone mineral density (BMD screening in the previous year than were bisphosphonate patients, and were also more likely to have used estrogen or estrogen/progestin therapy in the

  19. An interagency space nuclear propulsion safety policy for SEI - Issues and discussion

    Science.gov (United States)

    Marshall, A. C.; Sawyer, J. C., Jr.

    1991-01-01

    An interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition, the NSPWG reviewed safety issues for nuclear propulsion and recommended top level safety requirements and guidelines to address these issues. Safety topics include reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations. In this paper the emphasis is placed on the safety policy and the issues and considerations that are addressed by the NSPWG recommendations.

  20. Core competencies for patient safety research: a cornerstone for global capacity strengthening

    Science.gov (United States)

    Andermann, Anne; Ginsburg, Liane; Norton, Peter; Arora, Narendra; Bates, David; Wu, Albert

    2011-01-01

    Background Tens of millions of patients worldwide suffer disabling injuries or death every year due to unsafe medical care. Nonetheless, there is a scarcity of research evidence on how to tackle this global health priority. The shortage of trained researchers is a major limitation, particularly in developing and transitional countries. Objectives As a first step to strengthen capacity in this area, the authors developed a set of internationally agreed core competencies for patient safety research worldwide. Methods A multistage process involved developing an initial framework, reviewing the existing literature relating to competencies in patient safety research, conducting a series of consultations with potential end users and international experts in the field from over 35 countries and finally convening a global consensus conference. Results An initial draft list of competencies was grouped into three themes: patient safety, research methods and knowledge translation. The competencies were considered by the WHO Patient Safety task force, by potential end users in developing and transitional countries and by international experts in the field to be relevant, comprehensive, clear, easily adaptable to local contexts and useful for training patient safety researchers internationally. Conclusions Reducing patient harm worldwide will require long-term sustained efforts to build capacity to enable practical research that addresses local problems and improves patient safety. The first edition of Competencies for Patient Safety Researchers is proposed by WHO Patient Safety as a foundation for strengthening research capacity by guiding the development of training programmes for researchers in the area of patient safety, particularly in developing and transitional countries, where such research is urgently needed. PMID:21228081

  1. Nuclear safety review for the year 2000

    International Nuclear Information System (INIS)

    2001-06-01

    The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

  2. Risk-informed, performance-based safety-security interface

    International Nuclear Information System (INIS)

    Mrowca, B.; Eltawila, F.

    2012-01-01

    Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

  3. Patient safety culture in Norwegian nursing homes.

    Science.gov (United States)

    Bondevik, Gunnar Tschudi; Hofoss, Dag; Husebø, Bettina Sandgathe; Deilkås, Ellen Catharina Tveter

    2017-06-20

    Patient safety culture concerns leader and staff interaction, attitudes, routines, awareness and practices that impinge on the risk of patient-adverse events. Due to their complex multiple diseases, nursing home patients are at particularly high risk of adverse events. Studies have found an association between patient safety culture and the risk of adverse events. This study aimed to investigate safety attitudes among healthcare providers in Norwegian nursing homes, using the Safety Attitudes Questionnaire - Ambulatory Version (SAQ-AV). We studied whether variations in safety attitudes were related to professional background, age, work experience and mother tongue. In February 2016, 463 healthcare providers working in five nursing homes in Tønsberg, Norway, were invited to answer the SAQ-AV, translated and adapted to the Norwegian nursing home setting. Previous validation of the Norwegian SAQ-AV for nursing homes identified five patient safety factors: teamwork climate, safety climate, job satisfaction, working conditions and stress recognition. SPSS v.22 was used for statistical analysis, which included estimations of mean values, standard deviations and multiple linear regressions. P-values safety factors teamwork climate, safety climate, job satisfaction and working conditions. Not being a Norwegian native speaker was associated with a significantly higher mean score for job satisfaction and a significantly lower mean score for stress recognition. Neither professional background nor work experience were significantly associated with mean scores for any patient safety factor. Patient safety factor scores in nursing homes were poorer than previously found in Norwegian general practices, but similar to findings in out-of-hours primary care clinics. Patient safety culture assessment may help nursing home leaders to initiate targeted quality improvement interventions. Further research should investigate associations between patient safety culture and the occurrence

  4. Seismic safety margins research program overview

    International Nuclear Information System (INIS)

    Tokarz, F.J.; Smith, P.D.

    1978-01-01

    A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

  5. COLD-SAT feasibility study safety analysis

    Science.gov (United States)

    Mchenry, Steven T.; Yost, James M.

    1991-01-01

    The Cryogenic On-orbit Liquid Depot-Storage, Acquisition, and Transfer (COLD-SAT) satellite presents some unique safety issues. The feasibility study conducted at NASA-Lewis desired a systems safety program that would be involved from the initial design in order to eliminate and/or control the inherent hazards. Because of this, a hazards analysis method was needed that: (1) identified issues that needed to be addressed for a feasibility assessment; and (2) identified all potential hazards that would need to be controlled and/or eliminated during the detailed design phases. The developed analysis method is presented as well as the results generated for the COLD-SAT system.

  6. Development of photovoltaic array and module safety requirements

    Science.gov (United States)

    1982-01-01

    Safety requirements for photovoltaic module and panel designs and configurations likely to be used in residential, intermediate, and large-scale applications were identified and developed. The National Electrical Code and Building Codes were reviewed with respect to present provisions which may be considered to affect the design of photovoltaic modules. Limited testing, primarily in the roof fire resistance field was conducted. Additional studies and further investigations led to the development of a proposed standard for safety for flat-plate photovoltaic modules and panels. Additional work covered the initial investigation of conceptual approaches and temporary deployment, for concept verification purposes, of a differential dc ground-fault detection circuit suitable as a part of a photovoltaic array safety system.

  7. Introduction to South Africa's safety classification

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Kyung Jun; Wu, Sang Ik; Yoon, Juh Yeon [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    The safety functions of nuclear reactor facilities such as research reactors have to be maintained for all initiating events, incidents and accidents. From the position of licensee, it is a very important issue and design challenge to meet the licensing requirements for the final goal of proper safety functions from nuclear regulator. This paper intends to introduce and understand South Africa's licensing requirements and processing for safety classification of SSCs. South Africa's licensing requirements are shown in Table 1. Three categories A, B and C are categorized based on the occurrence frequency and the dose limitation of worker and public exposure. The Defense in Depth (DiD) and ALARA principle are forced to apply to a nuclear reactor facility design. Also, South Africa's safety and quality class compare with that of ANSI 51.1.

  8. Safety and licensing of nuclear heating plants

    International Nuclear Information System (INIS)

    Snell, V.G.; Hilborn, J.W.; Lynch, G.F.; McAuley, S.J.

    1989-09-01

    World attention continues to focus on nuclear district heating, a low-cost energy from a non-polluting fuel. It offers long-term security for countries currently dependent on fossil fuels, and can reduce the burden of fossil fuel transportation on railways and roads. Current initiatives encompass large, centralized heating plants and small plants supplying individual institutions. The former are variants of their power reactor cousins but with enhanced safety features. The latter face the safety and licensing challenges of urban siting and remotely monitored operation, through use of intrinsic safety features such as passive decay heat removal, low stored energy and limited reactivity speed and depth in the control systems. Small heating reactor designs are compared, and the features of the SLOWPOKE Energy System, in the forefront of these designs, are summarized. The challenge of public perception must be met by clearly presenting the characteristics of small heating reactors in terms of scale and transparent safety in design and operation, and by explaining the local benefits

  9. Creating a culture of safety: why CEOs hold the key to improved outcomes.

    Science.gov (United States)

    Birk, Susan

    2009-01-01

    When the nonprofit VHA foundation, created by VHA Inc., Irving, Texas, embarked on a national patient safety initiative it looked first to outside industries, gathering information and ideas from pioneers in nuclear energy, aviation, the military and other innovation-rich fields known for safety excellence.

  10. Exercise of the management of a crisis initiated by a malevolent act

    International Nuclear Information System (INIS)

    Nannini, Alerio; Aurelle, Jacques

    2010-01-01

    In addition to exercises performed in the field of security, it was decided, in agreement with the competent authorities in charge of safety and security to achieve an exercise in the field of safety with a terrorist attack of a nuclear power plant as initiator. The security exercises are in fact primarily designed to test coordination and response of various entities involved in responding to a malicious attack on a nuclear facility, the safety ''part'' being merely simulated. It was interesting to supplement this approach with an exercise to play the interface between safety and security in which the response - in term of security - would the simulated. The specifics of such an exercise are: - The initiator of the degradation of the facility safety being malicious, the sequences of equipment failures may be different from those resulting from a classical safety scenario; - a number of movements and actions on the site are prohibited because of the presence of attackers; - treatment time of the threat should be taken into account in assessing the return time of installation in a safe condition. Moreover, such an exercise should not lead to exchanges of sensitive information (on the threat or on the vulnerability of the facility or its components), it is presented as a series of degraded states of the installation which should be considered. The first such exercise took place one French NPP November 26, 2009. It is part of nuclear security drills conducted at the request of the ASN. This paper is focused on the security aspect in the sense of protection against malicious acts. (orig.)

  11. Safety And Transient Analyses For Full Core Conversion Of The Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Luong Ba Vien; Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong

    2011-01-01

    Preparing for full core conversion of Dalat Nuclear Research Reactor (DNRR), safety and transient analyses were carried out to confirm about ability to operate safely of proposed Low Enriched Uranium (LEU) working core. The initial LEU core consisting 92 LEU fuel assemblies and 12 Beryllium rods was analyzed under initiating events of uncontrolled withdrawal of a control rod, cooling pump failure, earthquake and fuel cladding fail. Working LEU core response were evaluated under these initial events based on RELAP/Mod3.2 computer code and other supported codes like ORIGEN, MCNP and MACCS2. Obtained results showed that safety of the reactor is maintained for all transients/accidents analyzed. (author)

  12. Fuel safety research 2001

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and the Reactor Fuel Examination Facility (RFEF) of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The laboratory consists of following five research groups corresponding to each research fields; Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). Research group of fuel behavior analysis (FEMAXI group). Research group of radionuclides release and transport behavior from irradiated fuel under severe accident conditions (VEGA group). The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents. This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory. (author)

  13. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report from Norway

    International Nuclear Information System (INIS)

    2006-05-01

    This report is the Norwegian report to the second review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The comments, questions and remarks given to Norway's initial national report and Norway's presentation given at the first review meeting have been incorporated in this report. The second report is a full revision of the first report. This report concludes that Norway meets the obligations of the Joint Convention. However, Norwegian authorities will aim for development in the waste management policy and Norway will continue to improve its existing systems to further enhance safety, in line with the aims of the Joint Convention

  14. Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

    International Nuclear Information System (INIS)

    1987-07-01

    The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

  15. National Partnership for Maternal Safety Consensus Bundle on Obstetric Hemorrhage.

    Science.gov (United States)

    Main, Elliott K; Goffman, Dena; Scavone, Barbara M; Low, Lisa Kane; Bingham, Debra; Fontaine, Patricia L; Gorlin, Jed B; Lagrew, David C; Levy, Barbara S

    2015-01-01

    Hemorrhage is the most frequent cause of severe maternal morbidity and preventable maternal mortality and therefore is an ideal topic for the initial national maternity patient safety bundle. These safety bundles outline critical clinical practices that should be implemented in every maternity unit. They are developed by multidisciplinary work groups of the National Partnership for Maternal Safety under the guidance of the Council on Patient Safety in Women's Health Care. The safety bundle is organized into 4 domains: Readiness, Recognition and Prevention, Response, and Reporting and Systems Learning. Although the bundle components may be adapted to meet the resources available in individual facilities, standardization within an institution is strongly encouraged. References contain sample resources and "Potential Best Practices" to assist with implementation. © 2015 by the American College of Obstetricians and Gynecologists.

  16. Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

    International Nuclear Information System (INIS)

    Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

    2001-01-01

    Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

  17. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 2, January 2007

    International Nuclear Information System (INIS)

    2006-08-01

    This newsletter reports on the training of cardiologists in radiation protection, IAEA's safety review services and the operational safety assessment review team (OSART), the international conference on management of spent fuel and the recent INSAG (International Nuclear Safety Group) publications. The IAEA has begun a major international initiative to train interventional cardiologists in radiation protection. Starting with the first course in May 2004, so far 6 regional and 3 national training courses have been conducted with the participation of over 400 health professionals putting the IAEA in a leading role in this area. A programme of two days' training has been developed, covering possible and observed radiation effects among patients and staff, international standards, dose management techniques, examples of good and bad practice and examples indicating prevention of possible injuries as a result of good practice in radiation protection. The training material is freely available on CD and will be placed on the Radiological Protection of Patients website at http://rpop.iaea.org/

  18. Nuclear safety: operational aspects. 3. Hazard Analysis of Passive Systems

    International Nuclear Information System (INIS)

    Burgazzi, Luciano

    2001-01-01

    Interest has been aroused in recent years regarding the reliability assessment of passive systems being developed by suppliers, industries, utilities, and research organizations that aim at plant safety improvement and substantial simplification in its implementation. The approach to passive systems reliability assessment entails first a detailed system and safety analysis, and failure mode and effect analysis (FMEA) methodology has been chosen to perform the safety analysis at the system level. The FMEA technique allows identification of all potential failure modes in a system to evaluate their effects on the system and to classify them according to their severity; this technique identifies the reliability-critical areas in the system where modifications to the design are required to reduce the probability of failure. The present study concerns passive systems designed for decay heat removal relying on natural circulation that foresee, for the most part, a condenser immersed in a cooling pool. This is to identify and rank by importance the potential hazards related to passive-system equipment and operation that may critically affect the safety or availability of the plant. More specifically, the content of the paper analyzes the isolation condenser (IC) system foreseen for advanced boiling water reactors for removal of excess sensible and core decay heat by natural circulation during isolation transients. This FMEA analysis is the initial step to be accomplished as support for the development of a methodology aimed at the reliability assessment of thermal-hydraulic passive safety systems, providing important input to more detailed quantitative studies employing, for instance, event trees and fault trees or other reliability/availability models. Main purposes of the work are to identify important accident initiators, find out the possible consequences on the plant deriving from component failures, individuate possible causes, identify mitigating features and

  19. Safety assessment of allylalkoxybenzene derivatives used as flavouring substances - methyl eugenol and estragole

    NARCIS (Netherlands)

    Smith, R.L.; Adams, T.B.; Doull, J.; Feron, V.J.; Goodman, J.I.; Marnett, L.J.; Portoghese, P.S.; Waddell, W.J.; Wagner, B.M.; Rogers, A.E.; Caldwell, J.; Sipes, I.G.

    2002-01-01

    This publication is the seventh in a series of safety evaluations performed by the Expert Panel of the Flavor and Extract Manufacturers' Association (FEMA). In 1993, the Panel initiated a comprehensive program to re-evaluate the safety of more than 1700 GRAS flavouring substances under conditions of

  20. Patient Safety in Pediatrics: a Developing Discipline

    NARCIS (Netherlands)

    C. van der Starre (Cynthia)

    2011-01-01

    markdownabstract__Abstract__ The publication of the breakthrough report “To Err is Human” by the Institute of Medicine was the launch of patient safety initiatives all over the world. In the intensive care unit (ICU) of the Erasmus MC-Sophia Children’s Hospital this resulted in the institution

  1. 47 CFR Appendix B to Part 400 - Initial Certification for E-911 Grant Applicants

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Initial Certification for E-911 Grant... ADMINISTRATION, DEPARTMENT OF COMMERCE, AND NATIONAL HIGHWAY TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION E-911 GRANT PROGRAM Pt. 400, App. B Appendix B to Part 400—Initial Certification for E-911 Grant...

  2. The association between event learning and continuous quality improvement programs and culture of patient safety.

    Science.gov (United States)

    Mazur, Lukasz; Chera, Bhishamjit; Mosaly, Prithima; Taylor, Kinley; Tracton, Gregg; Johnson, Kendra; Comitz, Elizabeth; Adams, Robert; Pooya, Pegah; Ivy, Julie; Rockwell, John; Marks, Lawrence B

    2015-01-01

    To present our approach and results from our quality and safety program and to report their possible impact on our culture of patient safety. We created an event learning system (termed a "good catch" program) and encouraged staff to report any quality or safety concerns in real time. Events were analyzed to assess the utility of safety barriers. A formal continuous quality improvement program was created to address these reported events and make improvements. Data on perceptions of the culture of patient safety were collected using the Agency for Health Care Research and Quality survey administered before, during, and after the initiatives. Of 560 good catches reported, 367 could be ascribed to a specific step on our process map. The calculated utility of safety barriers was highest for those embedded into the pretreatment quality assurance checks performed by physicists and dosimetrists (utility score 0.53; 93 of 174) and routine checks done by therapists on the initial day of therapy. Therapists and physicists reported the highest number of good catches (24% each). Sixty-four percent of events were caused by performance issues (eg, not following standardized processes, including suboptimal communications). Of 31 initiated formal improvement events, 26 were successfully implemented and sustained, 4 were discontinued, and 1 was not implemented. Most of the continuous quality improvement program was conducted by nurses (14) and therapists (7). Percentages of positive responses in the patient safety culture survey appear to have increased on all dimensions (p continuous quality improvement programs can be successfully implemented and that there are contemporaneous improvements in the culture of safety. Copyright © 2015 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  3. The directive establishing a community framework for the nuclear safety of nuclear installations: the European Union approach to nuclear safety

    International Nuclear Information System (INIS)

    Garribba, M.; Chirtes, A.; Nauduzaite, M.

    2009-01-01

    This article aims at explaining the evolution leading to the adoption of the recent Council Directive 2009/71/EURATOM establishing a Community framework for the nuclear safety of nuclear installations adopted with the consent of all 27 members states following the overwhelming support of the European Parliament, that creates for the first time, a binding legal framework that brings legal certainty to European Union citizens and reinforces the role and independence of national regulators. The paper is divided into three sections. The first section addresses the competence of the European Atomic energy Community to legislate in the area of nuclear safety. It focuses on the 2002 landmark ruling of the European Court of justice that confirmed this competence by recognizing the intrinsic link between radiation protection and nuclear safety. The second part describes the history of the Nuclear safety directive from the initial 2003 European Commission proposal to today 's text in force. The third part is dedicated to a description of the content of the Directive and its implications on the further development of nuclear safety in the European Union. (N.C.)

  4. Organisational readiness: exploring the preconditions for success in organisation-wide patient safety improvement programmes.

    Science.gov (United States)

    Burnett, Susan; Benn, Jonathan; Pinto, Anna; Parand, Anam; Iskander, Sandra; Vincent, Charles

    2010-08-01

    Patient safety has been high on the agenda for more than a decade. Despite many national initiatives aimed at improving patient safety, the challenge remains to find coherent and sustainable organisation-wide safety-improvement programmes. In the UK, the Safer Patients' Initiative (SPI) was established to address this challenge. Important in the success of such an endeavour is understanding 'readiness' at the organisational level, identifying the preconditions for success in this type of programme. This article reports on a case study of the four NHS organisations participating in the first phase of SPI, examining the perceptions of organisational readiness and the relationship of these factors with impact by those actively involved in the initiative. A mixed-methods design was used, involving a survey and semistructured interviews with senior executive leads, the principal SPI programme coordinator and the four operational leads in each of the SPI clinical work areas in all four organisations taking part in the first phase of SPI. This preliminary work would suggest that prior to the start of organisation-wide quality- and safety-improvement programmes, organisations would benefit from an assessment of readiness with time spent in the preparation of the organisational infrastructure, processes and culture. Furthermore, a better understanding of the preconditions that mark an organisation as ready for improvement work would allow policymakers to set realistic expectations about the outcomes of safety campaigns.

  5. Plutonium safety training course

    International Nuclear Information System (INIS)

    Moe, H.J.

    1976-03-01

    This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the transplutonium nuclides relative to 239 Pu follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed

  6. Probabilistic analysis of safety in industrial irradiation plants

    International Nuclear Information System (INIS)

    Alderete, F.; Elechosa, C.

    2006-01-01

    The Argentinean Nuclear Regulatory Authority is carrying out the Probabilistic Safety Analysis (PSA) of the two industrial irradiation plants existent in the country. The objective of this presentation is to show from the regulatory point of view, the advantages of applying this tool, as well as the appeared difficulties; for it will be made a brief description of the facilities, of the method and of the normative one. Both plants are multipurpose facilities classified as 'industrial irradiator category IV' (panoramic irradiator with source deposited in pool). Basically, the execution of an APS consists of the following stages: 1. Identification of initiating events. 2. Modeling of Accidental Sequences (Event Trees). 3. Analysis of Systems (Fault trees). 4. Quantification of Accidental Sequences. The argentine normative doesn't demand to these facilities the realization of an APS, however the basic standard of Radiological Safety establishes that in the design of this type of facilities in the cases that is justified, should make sure that the annual probability of occurrence of an accidental sequence and the resulting dose in a person gives as result an radiological risk inferior to the risk limit adopted as acceptance criteria. On the other hand the design standard specifies for these irradiators it demands a maximum fault rate of 10 -2 for the related components with the systems of radiological safety. In our case, the possible initiating events have been identified that carried out to not wanted situations (about people exposure, radioactive contamination). Then, for each one of the significant initiating events, the corresponding accidental sequences were modeled and the safety systems that intervene in this sequences by means of fault trees were analyzed, for then to determine the fault probabilities of the same ones. At the moment they are completing these fault trees, but the difficulty resides in the impossibility of obtaining real data of the reliability

  7. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

    International Nuclear Information System (INIS)

    1994-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  8. Organisation of safety research programmes and infrastructure for existing reactors

    International Nuclear Information System (INIS)

    Micaelli, J.C.

    2008-01-01

    The author reviewed the main drivers of safety research, noting that challenging research is an excellent means to preserve know-how and professional skills. International efforts such the NEA-CSNI joint projects are an efficient means to support experimental infrastructure for safety research, while providing useful experimental results. Other initiatives, e.g. within the EU, aimed at developing networks of international expertise and infrastructure were also mentioned. (author)

  9. Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

    International Nuclear Information System (INIS)

    Laub, T.W.; Jardine, L.J.

    1987-01-01

    A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-care vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

  10. Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

    International Nuclear Information System (INIS)

    Laub, T.W.; Jardine, L.J.

    1987-01-01

    A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-car vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

  11. Periodic safety reviews of nuclear power plants

    International Nuclear Information System (INIS)

    Toth, Csilla

    2009-01-01

    Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

  12. Predisposal Management of Low and Intermediate Level Radioactive Waste. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established for the predisposal management of low and intermediate level waste. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. General safety considerations; 5. Safety features for the predisposal management of LILW; 6. Record keeping and reporting; 7. Safety assessment; 8. Quality assurance; Annex I: Nature and sources of LILW from nuclear facilities; Annex II: Development of specifications for waste packages; Annex III: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Postulated initiating events for consideration in a safety assessment (internal phenomena).

  13. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF.

  14. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF

  15. Identification of human-induced initiating events in the low power and shutdown operation using the commission error search and assessment method

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Chan; Kim, Jong Hyun [KEPCO International Nuclear Graduate School (KINGS), Ulsan (Korea, Republic of)

    2015-03-15

    Human-induced initiating events, also called Category B actions in human reliability analysis, are operator actions that may lead directly to initiating events. Most conventional probabilistic safety analyses typically assume that the frequency of initiating events also includes the probability of human-induced initiating events. However, some regulatory documents require Category B actions to be specifically analyzed and quantified in probabilistic safety analysis. An explicit modeling of Category B actions could also potentially lead to important insights into human performance in terms of safety. However, there is no standard procedure to identify Category B actions. This paper describes a systematic procedure to identify Category B actions for low power and shutdown conditions. The procedure includes several steps to determine operator actions that may lead to initiating events in the low power and shutdown stages. These steps are the selection of initiating events, the selection of systems or components, the screening of unlikely operating actions, and the quantification of initiating events. The procedure also provides the detailed instruction for each step, such as operator's action, information required, screening rules, and the outputs. Finally, the applicability of the suggested approach is also investigated by application to a plant example.

  16. Indicators of Faculty and Staff Perceptions of Campus Safety: A Case Study

    Science.gov (United States)

    Woolfolk, Willie A.

    2013-01-01

    The study addressed the problem of a critical increase in campus crime between 1999 and 2009, a period during which overall crime in the United States declined. Further the research explored the perceptions of campus safety among faculty and staff at an institution where campus safety initiatives are nationally ranked as exemplary and incidents of…

  17. An Approach to Enhancement of the Safety Culture of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an initiation plan to study the safety culture issue in Korean NPPs. Recently there happened successively events that turned out to be socially prominent in Korea. Many issues on the safety culture aspect of NPPs have been raised including the types of errors such as violations, an intended concealment of safety-related information, counterfeit items, forgery process in procurement, and so on. Those were investigated in detail for the root causes of these issues as human and organizational errors and for the countermeasures to prevent those events. They are integrated into a correspondent long-term plan including the establishment of a fundamental infrastructure of safety culture management for operating NPPs in Korea. A monitoring system with analysis functions utilizing system dynamics simulation and data mining is proposed to be incorporated into a safety culture management system. Additionally, a set of training and support programs are to be developed for the enhancement of some selected competence of the operating personnel in Korean NPPs. The safe operation of NPPs requires the typical safety culture characteristics of the high reliability organization (HRO). The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an integrated systems approach as an initiating plan to study the safety culture issue in Korean NPPs.

  18. An Approach to Enhancement of the Safety Culture of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee

    2014-01-01

    The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an initiation plan to study the safety culture issue in Korean NPPs. Recently there happened successively events that turned out to be socially prominent in Korea. Many issues on the safety culture aspect of NPPs have been raised including the types of errors such as violations, an intended concealment of safety-related information, counterfeit items, forgery process in procurement, and so on. Those were investigated in detail for the root causes of these issues as human and organizational errors and for the countermeasures to prevent those events. They are integrated into a correspondent long-term plan including the establishment of a fundamental infrastructure of safety culture management for operating NPPs in Korea. A monitoring system with analysis functions utilizing system dynamics simulation and data mining is proposed to be incorporated into a safety culture management system. Additionally, a set of training and support programs are to be developed for the enhancement of some selected competence of the operating personnel in Korean NPPs. The safe operation of NPPs requires the typical safety culture characteristics of the high reliability organization (HRO). The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an integrated systems approach as an initiating plan to study the safety culture issue in Korean NPPs

  19. 78 FR 41689 - Safety Zone; Skagit River Bridge, Skagit River, Mount Vernon, WA

    Science.gov (United States)

    2013-07-11

    ... submerged automobiles and floating bridge debris in the Skagit River. Following the initial response and...-AA00 Safety Zone; Skagit River Bridge, Skagit River, Mount Vernon, WA AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a safety zone around the Skagit River Bridge...

  20. Enhancing the Safety and Security of Radioactive Sources

    International Nuclear Information System (INIS)

    Hickey, J.

    2004-01-01

    The NRC initiatives to improve safety and security of sources began before 091101 and include both international and domestic activities. They supported the development and implementation of the IAEA Code of Conduct, which provides categorization of sources of concern, based on risk, improvement of regulatory programs of all member countries and improvement of safety and security of sources. International activities include the IAEA International Conference on Security of Sources (Vienna, Austria, March, 2003), the trilateral cooperation with Canada and Mexico, the assistance to individual countries to improve security and the proposed rule on export and import of radioactive material. The domestic initiatives are to issue the security orders and advisories to licensees, issue the panoramic irradiator orders (June 2003), issue the manufacturer orders (January 2004), complete the interim national source inventory, develop the national source tracking system, maintain the orphan source registration and retrieval program and upgrade the emergency preparedness

  1. Safety analysis of Ignalina NPP during shutdown conditions

    International Nuclear Information System (INIS)

    Kaliatka, A.; Uspuras, E.

    2000-01-01

    The accident analysis for the Ignalina NPP with RBMK-1500 reactors at normal operating conditions and at minimum controlled power level (during startup of the reactor) has been performed in the frame of the project I n-Depth Safety Assessment of the Ignalina NPP , which was completed in 1996. However, the plant conditions during the reactor shutdown differ from conditions during reactor operation at full power (equipment status in protection systems, set points for actuation of safety and protection systems, etc.). Results of RELAP5 simulation of two worst initiating events during reactor shutdown - Pressure Header rupture in case of steam reactor cooldown as well as Pressure Header rupture in case of water reactor cooldown are discussed in the paper. Results of analysis shown that reactor are reliably cooled in both cases. Further analysis for all range of initial events during reactor shutdown and at shutdown conditions is recommended. (author)

  2. Safety case: An international perspective

    International Nuclear Information System (INIS)

    Pescatore, C.; Voinis, S.

    2002-01-01

    In recent years, it has become more and more evident that repository development will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical arguments that will help in giving confidence in the feasibility and safety of the proposed concept. The depth of understanding and technical information available to support decisions will vary from step to step. A safety case is a key item to support the decision to move to the next stage in repository development. Progress is noted, in the past decade, in the performance and safety assessment areas, particularly in the methodologies for repository system analysis. Progress is also observed regarding the understanding of the natural system and its characterisation, treatment of uncertainties, and modelling. Some areas are under active development, e.g. the area of scenario development and analysis. Finally, to increase confidence, rigorous quality assurance procedures need to be implemented, as well as the factoring of the contribution of R and D in underground research laboratories. The paper summarises the lessons learnt within relevant NEA initiatives as they evolved over the course of a decade and now allow a comprehensive view of what constitutes a safety case. (author)

  3. The evaluation of research reactor TRIGA MARK II safety

    International Nuclear Information System (INIS)

    Jordan, R.; Kozuh, M.; Mavko, B.

    1994-01-01

    In the paper the Probabilistic Safety Analysis (PSA) of a research reactor is described. Five different initiating events were selected and analyzed with the use of event trees. Seven reactor systems were modeled with fault trees. Three groups of radiation releases were introduced - Success, Reactor-Hall, Environment - and their frequencies were estimated. The importance factors of initiating events, human errors and basic events were calculated regarding the consequence groups. (author)

  4. Inherent safety characteristics of innovative reactors

    International Nuclear Information System (INIS)

    Heil, J.A.

    1995-11-01

    The added safety value of innovative or third generation reactor designs has been evaluated in order to determine the most suitable candidate for Dutch government funded research and development support. To this end, four innovative reactor concepts, viz. PIUS (Process Inherent Ultimate Safety), PRISM (Power Reactor Innovative Small), HTR-M (High Temperature Reactor Module) and MHTGR (Modular High Temperature Gas-cooled Reactor), have been studied and their passive and inherent safety characteristics have been outlined. Also the outlook for further technological and industrial development has been considered. The results of the study confirm the perspective of the innovative reactors for reduced dependence on active safety provisions and for a further reduced vulnerability to technical failures and human errors. The accident responses to generic accident initiators, viz. reactivity and cooling accidents, and also to reactor specific accidents show that neither active safety systems nor short term operator actions are required for maintaining the reactor core in a controlled and coolable condition. Whether this gives rise to a higher total safety of the innovative reactor designs, compared to evolutionary or advanced reactors, cannot be concluded. Supplementary experimental and analytical analyses of reactor specific accidents are required to be able to assess the safety of these innovative designs in a more quantitative manner. It is believed that the safety case of innovative reactors, which are less dependent on active safety systems, can be communicated with the general public in a more transparent way. Considering the perspective for further technological and industrial development it is not expected that any of the considered innovative reactor concepts will become commercially available within the next one to two decades. However, they could be made available earlier if they would receive sufficient financial backing. Considering the added safety perspectives

  5. Innovative Patient Safety Curriculum Using iPAD Game (PASSED) Improved Patient Safety Concepts in Undergraduate Medical Students.

    Science.gov (United States)

    Kow, A W C; Ang, B L S; Chong, C S; Tan, W B; Menon, K R

    2016-11-01

    While healthcare outcomes have improved significantly, the complex management of diseases in the hospitals has also escalated the risks in patient safety. Therefore, in the process of training medical students to be proficient in medical knowledge and skills, the importance of patient safety cannot be neglected. A new innovation using mobile apps gaming system (PAtient Safety in Surgical EDucation-PASSED) to teach medical students on patient safety was created. Students were taught concepts of patient safety followed by a gaming session using iPad games created by us. This study aims to evaluate the outcome of patient safety perception using the PASSED games created. An interactive iPad game focusing on patient safety issues was created by the undergraduate education team in the Department of Surgery, Yong Loo Lin School of Medicine at the National University of Singapore. The game employed the unique touched-screen feature with clinical scenarios extracted from the hospital sentinel events. Some of the questions were time sensitive, with extra bonus marks awarded if the student provided the correct answer within 10 s. Students could reattempt the questions if the initial answer was wrong. However, this entailed demerit points. Third-year medical students posted to the Department of Surgery experienced this gaming system in a cohort of 55-60 students. Baseline understanding of the students on patient safety was evaluated using Attitudes to Patient Safety Questionnaire III (APSQ-III) prior to the game. A 20 min talk on concept of patient safety using the WHO Patient Safety Guidelines was conducted. Following this, students downloaded the apps from ITune store and played with the game for 20-30 min. The session ended with the students completing the postintervention questionnaire. A total of 221 3rd year medical students responded to the survey during the PASSED session. Majority of the students felt that the PASSED game had trained them to understand the

  6. Safety training news

    CERN Multimedia

    Safety Training, HSE Unit

    2014-01-01

      SELF-RESCUE MASK The "Self-Rescue Mask" face-to-face training course has been replaced by a revised version. This measure concerns both the initial and the refresher course. For personnel who have successfully attended the initial or refresher Self-Rescue Mask training within the last three years, their Self-Rescue Mask training will still be valid.  The course description and registration form can be found in the training catalogue on the Safety Training Service’s website or catalogue. The Self-Rescue Mask training course is a mandatory prerequisite for following the new "Portable ODH Detector" e-learning course.   PORTABLE ODH DETECTOR A new e-learning awareness course, "Portable ODH Detector", is available via the SIR application on CERN’s intranet. Personnel requiring a portable ODH detector of the DRÄGER x-am 5000 type to allowed access th...

  7. Safety related experience in FFTF startup and operation

    International Nuclear Information System (INIS)

    Peterson, R.E.; Halverson, T.G.; Daughtry, J.W.

    1982-06-01

    The Fast Flux Test Facility (FFTF) is a 400 MW(t) sodium cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US LMFBR program. Startup and initial power ascension testing of the facility involved a comprehensive series of readiness reviews and acceptance tests, many of which relate to the inherent safety of the plant. Included are physics measurements, natural circulation, integrated containment leakage, shielding effectiveness, fuel failure detection, and plant protection system tests. Described are the measurements taken to confirm the design safety margins upon which the operating authorization of the plant was based. These measurements demonstrate that large margins of safety are available in the FFTF design

  8. ICT support safety, health and environment management system (e-SHEMS)

    International Nuclear Information System (INIS)

    Amy Hamijah Ab Hamid; Hasfazilah Hassan; Siti Massari Amran; Norzalina Nasirudin; Azimawati Ahmad; Mohd Suhaimi Kassim; Shaharum Ramli; Musa Ibrahim; Mohd Sidek Othman

    2009-01-01

    Safety program is compulsory for a nuclear technology related research and development institution like Nuclear Malaysia. It has been implemented in various safety standard systems including Act 514, Act 304, ISO 14000, OSHAS 18001 and IAEA. This paper began with Nuclear Malaysia history in initiating our own safety standard system since 1982. Currently, Nuclear Malaysia's Safety Health and Environment Management System (SHE-MS) was stipulated for similar purpose. Furthermore, it has implemented guidelines by AELB, IAEA, DOSH, Fire Brigade and Police Force. This paper briefly describes the overall structure of SHE-MS, how it functions and being managed, and lessons learned. The findings which are based on the issues and challenges, then it can be analysed to propose a development of SHE-MS ICT-support application for future improvement and enhancement in inculcating and nurturing safety culture among Nuclear Malaysia staff. (Author)

  9. Why does Safety Culture Matter?

    International Nuclear Information System (INIS)

    Dahlgren-Persson, Kerstin

    2008-01-01

    Dr. Kerstin Dahlgren-Persson, from the IAEA presented a plenary paper on 'Why does safety culture matter?'. The paper discussed the main conclusions of a 1998 IAEA conference on shortcomings in safety management. The conference included case studies of TVA, Cooper, Peach Bottom, Millstone, Ontario Hydro, Barsebaeck and Oskarshamn. Common symptoms included insularity; disproportionate focus on technical issues, high initial performance, lack of corporate oversight, changing management direction and cost cutting, repeat problems, and regulatory dissatisfaction. Behind these symptoms was lack of senior utility leadership with the insight, knowledge and ability to manage the unique interaction between the technology, economics, human factors and safety in a changing nuclear environment. Shortcomings relating to the regulator included lack of criteria for when regulatory actions should be taken in response to degradations in safety management, and the inability of some regulators to influence at the senior utility management level. The paper also made the following key points: - Human error is not always symptomatic of a poor safety culture. Effective root cause analysis (such as that carried out for the Columbia accident investigation) is essential to correctly differentiate between situational issues at a point in time and those rooted in organizational culture. - Leaders change culture by holding different assumptions and by making them visible through their words and action. - Regulators should consider how their regulatory strategy influences licensees. For example, a prescriptive strategy can foster a compliance based approach

  10. The French-German initiative for Chernobyl: Overview of the French-German initiative

    Energy Technology Data Exchange (ETDEWEB)

    Biesold, H.; Friederichs, H.G.; Pretzsch, G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Dept. International Programmes, Berlin (Germany); Deville-Cavelin, G.; Lhomme, V.; Rutschkowsky, N.; Tirmarche, M. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Dept. International Relations, 92 - Clamart (France); Bazyka, D.; Chabanyuk, V.; Seleznev, A. [Chornobyl Center (CC), Kiev regoin (Ukraine); Kellerer, A.M. [Munchen Univ., Strahlenbiologisches Institut (Germany)

    2006-07-01

    - Purpose: The main purpose of the French-German Initiative is to assist in the collection and validation of the existing data in Ukraine, Belarus and Russia for developing a reliable and objective basis useful for the planning of counter-measures, for information of the public, and for future work. - Coordination: GRS (Gesellschaft fuer Anlagen- und Reaktorsicherheit), supported in programme 3 by SBI (Strahlenbiologisches Institut der Universitaet Muenchen) and IRSN (Institut de radioprotection et de surete nucleaire) are coordinating the projects on the Western side. The CC (Chernobyl Center for Nuclear Safety, Radioactive Waste and Radioecology) as Eastern coordinator is also the beneficiary. German Support by Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit (BMU), Vereinigung Deutscher Elektrizitaetswerke (VDEW) e.V.; French Support by Institut de radioprotection et de surete nucleaire (IRSN), Electricite de France (EdF). - Programmes: Three scientific and technical co-operation programmes are financed with a total budget of about 6 million Euro within the frame work of the French- German Initiative: Programme 1: SARCOPHAGUS: Safety of the Chernobyl 'Sarcophagus', Programme 2: RADIOECOLOGY: Study of the radioecological consequences of the accident,Programme 3: HEALTH: Study of health effects. - Background: At the IAEA conference in Vienna in April 1996 - 10 years after the Chernobyl accident - the French and German Environment Ministers jointly announced their co-operation initiative with the Ukraine, Belarus and Russia over scientific programmes concerning the aftermath of the Chernobyl disaster. Numerous scientific studies have been conducted in the affected republics of the former USSR with and without the participation of international organisations, but largely with insufficient real co-ordination. For some of the studies, results have never been publicly documented. There are still incoherent or even contradictory reports on the

  11. Nonclinical cardiovascular safety of pitolisant: comparing International Conference on Harmonization S7B and Comprehensive in vitro Pro-arrhythmia Assay initiative studies.

    Science.gov (United States)

    Ligneau, Xavier; Shah, Rashmi R; Berrebi-Bertrand, Isabelle; Mirams, Gary R; Robert, Philippe; Landais, Laurent; Maison-Blanche, Pierre; Faivre, Jean-François; Lecomte, Jeanne-Marie; Schwartz, Jean-Charles

    2017-12-01

    We evaluated the concordance of results from two sets of nonclinical cardiovascular safety studies on pitolisant. Nonclinical studies envisaged both in the International Conference on Harmonization (ICH) S7B guideline and Comprehensive in vitro Pro-arrhythmia Assay (CiPA) initiative were undertaken. The CiPA initiative included in vitro ion channels, stem cell-derived human ventricular myocytes, and in silico modelling to simulate human ventricular electrophysiology. ICH S7B-recommended assays included in vitro hERG (K V 11.1) channels, in vivo dog studies with follow-up investigations in rabbit Purkinje fibres and the in vivo Carlsson rabbit pro-arrhythmia model. Both sets of nonclinical data consistently excluded pitolisant from having clinically relevant QT-liability or pro-arrhythmic potential. CiPA studies revealed pitolisant to have modest calcium channel blocking and late I Na reducing activities at high concentrations, which resulted in pitolisant reducing dofetilide-induced early after-depolarizations (EADs) in the ICH S7B studies. Studies in stem cell-derived human cardiomyocytes with dofetilide or E-4031 given alone and in combination with pitolisant confirmed these properties. In silico modelling confirmed that the ion channel effects measured are consistent with results from both the stem cell-derived cardiomyocytes and rabbit Purkinje fibres and categorized pitolisant as a drug with low torsadogenic potential. Results from the two sets of nonclinical studies correlated well with those from two clinical QT studies. Our findings support the CiPA initiative but suggest that sponsors should consider investigating drug effects on EADs and the use of pro-arrhythmia models when the results from CiPA studies are ambiguous. © 2017 The Authors. British Journal of Pharmacology published by John Wiley & Sons Ltd on behalf of British Pharmacological Society.

  12. Management Oversight and Risk Tree (MORT): a new system safety program

    International Nuclear Information System (INIS)

    Clark, J.L.

    Experiences of Aerojet Nuclear Company (ANC), in the development and implementation of a system safety program for ANC and for the Energy Research and Development Administration (ERDA) are discussed. Aerojet Nuclear is the prime operating contractor for ERDA, formerly AEC, at the Idaho National Engineering Laboratory. The ERDA sponsored ''MORT'' system safety program is described along with the process whereby formal system safety methods are incorporated into a stable organization. Specifically, a discussion is given of initial development of MORT; pilot program trials conducted at ANC; implementation methodology; and reaction of the ANC organization. (auth)

  13. Assuring safety without animal testing: Unilever's ongoing research programme to deliver novel ways to assure consumer safety.

    Science.gov (United States)

    Westmoreland, Carl; Carmichael, Paul; Dent, Matt; Fentem, Julia; MacKay, Cameron; Maxwell, Gavin; Pease, Camilla; Reynolds, Fiona

    2010-01-01

    Assuring consumer safety without the generation of new animal data is currently a considerable challenge. However, through the application of new technologies and the further development of risk-based approaches for safety assessment, we remain confident it is ultimately achievable. For many complex, multi-organ consumer safety endpoints, the development, evaluation and application of new, non-animal approaches is hampered by a lack of biological understanding of the underlying mechanistic processes involved. The enormity of this scientific challenge should not be underestimated. To tackle this challenge a substantial research programme was initiated by Unilever in 2004 to critically evaluate the feasibility of a new conceptual approach based upon the following key components: 1.Developing new, exposure-driven risk assessment approaches. 2.Developing new biological (in vitro) and computer-based (in silico) predictive models. 3.Evaluating the applicability of new technologies for generating data (e.g. "omics", informatics) and for integrating new types of data (e.g. systems approaches) for risk-based safety assessment. Our research efforts are focussed in the priority areas of skin allergy, cancer and general toxicity (including inhaled toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biology and molecular mechanisms that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement in EU-funded projects (e.g. Sens-it-iv, Carcinogenomics), participation in cross-industry collaborative research (e.g. Colipa, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US "Human Toxicology Project" consortium).

  14. 75 FR 57081 - Revised Draft Safety Culture Policy Statement: Request for Comments

    Science.gov (United States)

    2010-09-17

    ... culture. Experience has shown that certain personal and organizational traits are present in a positive safety culture. A trait, in this case, is a pattern of thinking, feeling, and behaving that emphasizes... organizational environments. IV. Changes to the Initial Draft Statement of Policy Like the initial draft SOP, the...

  15. Safety and environmental requirements and design targets for TIBER-II

    International Nuclear Information System (INIS)

    Piet, S.J.

    1987-09-01

    A consistent set of safety and environmental requirements and design targets was proposed and adopted for the TIBER-II (Tokamak Ignition/Burn Experimental Reactor) design effort. TIBER-II is the most recent US version of a fusion experimental test reactor (ETR). These safety and environmental design targets were one contribution of the Fusion Safety Program in the TIBER-II design effort. The other contribution, safety analyses, is documented in the TIBER-II design report. The TIBER-II approach, described here, concentrated on logical development of, first, a complete and consistent set of safety and environmental requirements that are likely appropriate for an ETR, and, second, an initial set of design targets to guide TIBER-II. Because of limited time in the TIBER-II design effort, the iterative process only included one iteration - one set of targets and one design. Future ETR design efforts should therefore build on these design targets and the associated safety analyses. 29 refs., 5 figs., 3 tabs

  16. Development of an FPGA-based controller for safety critical application

    International Nuclear Information System (INIS)

    Xing, A.; De Grosbois, J.; Sklyar, V.; Archer, P.; Awwal, A.

    2011-01-01

    In implementing safety functions, Field Programmable Gate Arrays (FPGA) technology offers a distinct combination of benefits and advantages over microprocessor-based systems. FPGAs can be designed such that the final product is purely hardware, without any overhead runtime software, bringing the design closer to a conventional hardware-based solution. On the other hand, FPGAs can implement more complex safety logic that would generally require microprocessor-based safety systems. There are now qualified FPGA-based platforms available on the market with a credible use history in safety applications in nuclear power plants. Atomic Energy of Canada (AECL), in collaboration with RPC Radiy, has initiated a development program to define a vigorous FPGA engineering process suitable for implementing safety critical functions at the application development level. This paper provides an update on the FPGA development program along with the proposed design model using function block diagrams for the development of safety controllers in CANDU applications. (author)

  17. Preparation of safety and regulatory document for BARC Facilities

    International Nuclear Information System (INIS)

    Prasad, S.S.; Jayarajan, K.

    2017-01-01

    In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

  18. Pulse coded safety logic for PFBR

    International Nuclear Information System (INIS)

    Anwer, Md. Najam; Satheesh, N.; Nagaraj, C.P.; Krishnakumar, B.

    2002-01-01

    Full text: Reactor safety logic is designed to initiate safety action against design basis events. The reactor is shutdown by de-energizing electromagnets and dropping the absorber rods under gravity. In prototype fast breeder reactor (PFBR), shutdown is affected by two independent shutdown systems, viz., control and safety rod drive mechanism (CSRDM) and diverse safety rod drive mechanism (DSRDM). Two separate safety logics are proposed for CSRDM and DSRDM, i.e. solid state logic with on-line fine impulse test (FIT) for CSRDM and pulse coded safety logic (PCSL) for DSRDM. The PCSL primarily utilizes the fact that the vast majority of faults in the logic circuitry result in static conditions at the output. It is arranged such that the presence of pulses are required to hold the shutdown actuators and any DC logic state, either logic 0 or logic 1 releases them. It is a dynamic, self-testing logic and used in a number of reactors. This paper describes the principle of operation of PCSL, its advantages, the concept of guard line logic (GLL), detection of stuck at 0 and stuck at 1 faults, fail safe and diversity features. The implementation of PCSL using Altera Max+Plus II software for PFBR trip signals and the results of simulation are discussed. This paper also describes a test jig using 80186 based system for testing PCSL for various input parameter's combinations and monitoring the outputs

  19. Study on operational safety issues in the Japanese disposal concept

    International Nuclear Information System (INIS)

    Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

    2014-01-01

    In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

  20. The French-German initiative for Chernobyl (FGI)

    Energy Technology Data Exchange (ETDEWEB)

    Biesold, H.; Friederichs, H.G.; Pretzsch, G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH, GRS, Schwertnergasse 1, D - 50667 Koeln (Germany); Deville-Cavelin, G.; Lhomme, V.; Rutschkowsky, N.; Tirmarche, M. [Institut de Radioprotection et de Surete Nucleaire, IRSN, B.P. 17, F - 92262 Fontenay-aux-Roses Cedex (France); Bazyka, D.; Chabanyuk, V.; Seleznev, A. [Radioactive Waste and Radioecology, Department Chernobyl Center for Nuclear Safety, Chernobylsk (Ukraine); Kellerer, A.M. [Strahlenbiologisches Institut der Universitaet Muenchen, Muenchen (Germany)

    2003-07-01

    Three scientific and technical co-operation programmes are financed with a total budget of about 6 million EURO within the framework of the French-German initiative: - Programme 1 - SARCOPHAGUS, referring to the safety of the Chernobyl 'SARCOPHAGUS'; - Programme 2 - RADIOECOLOGY, concerning the study of the radioecological consequences of the accident; - Programme 3 - HEALTH regarding the study of health effects. At the IAEA conference in Vienna in April 1996 - 10 years after the Chernobyl accident - the French and German Environment Ministers jointly announced their co-operation initiative with the Ukraine, Belarus and Russia over scientific programmes concerning the aftermath of the Chernobyl disaster. Numerous scientific studies have been conducted in the affected republics of the former USSR with and without the participation of international organisations, but largely with insufficient real coordination. For some of the studies, results have never been publicly documented. There are still incoherent or even contradictory reports on the ecological and medical consequences of the accident. The main purpose of the French-German initiative is to assist in the collection and validation of the existing data in Ukraine, Belarus and Russia for developing a reliable and objective basis useful for the planning of counter-measures, for information of the public, and for future work. GRS supported in program 3 by SBI (Strahlenbiologisches Institut der Universitaet Muenchen) and IRSN are coordinating the projects on the Western side. The CC (Radioactive Waste and Radioecology, Department Chernobyl Center for Nuclear Safety) as Eastern coordinator is also the beneficiary.

  1. Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

  2. Initial preclinical safety of non-replicating human endogenous retrovirus envelope protein-coated baculovirus vector-based vaccines against human papillomavirus.

    Science.gov (United States)

    Han, Su-Eun; Kim, Mi-Gyeong; Lee, Soondong; Cho, Hee-Jeong; Byun, Youngro; Kim, Sujeong; Kim, Young Bong; Choi, Yongseok; Oh, Yu-Kyoung

    2013-12-01

    Human endogenous retrovirus (HERV) envelope protein-coated, baculovirus vector-based HPV 16 L1 (AcHERV-HPV16L1) is a non-replicating recombinant baculoviral vaccine. Here, we report an initial evaluation of the preclinical safety of AcHERV-HPV16L1 vaccine. In an acute toxicity study, a single administration of AcHERV-HPV16L1 DNA vaccine given intramuscularly (i.m.) to mice at a dose of 1 × 10(8) plaque-forming units (PFU) did not cause significant changes in body weight compared with vehicle-treated controls. It did cause a brief increase in the weights of some organs on day 15 post-treatment, but by day 30, all organ weights were not significantly different from those in the vehicle-treated control group. No hematological changes were observed on day 30 post-treatment. In a range-finding toxicity study with three doses of 1 × 10(7) , 2 × 10(7) and 5 × 10(7) PFU once daily for 5 days, the group treated with 5 × 10(7) PFU showed a transient decrease in the body weights from day 5 to day 15 post-treatment, but recovery to the levels similar to those in the vehicle-treated control group by post-treatment day 20. Organ weights were slightly higher for lymph nodes, spleen, thymus and liver after repeated dosing with 5 × 10(7) PFU on day 15, but had normalized by day 30. Moreover, repeated administration of AcHERV-HPV16L1 did not induce myosin-specific autoantibody in serum, and did not cause immune complex deposition or tissue damage at injection sites. Taken together, these results provide preliminary evidence of the preclinical safety of AcHERV-based HPV16L1 DNA vaccines in mice. Copyright © 2012 John Wiley & Sons, Ltd.

  3. The FORO Project on Safety Culture in Organizations, Facilities and Activities With Sources of Ionizing Radiation

    International Nuclear Information System (INIS)

    Bomben, A. M.; Ferro Fernández, R.; Arciniega Torres, J.; Ordoñez Gutiérrez, E.; Blanes Tabernero, A.; Cruz Suárez, R.; Da Silva Silveira, C.; Perera Meas, J.; Ramírez Quijada, R.; Videla Valdebenito, R.

    2016-01-01

    The aim of this paper is to present the Ibero-American Forum of Nuclear and Radiological Regulatory Authorities’ (FORO) Project on Safety Culture in organizations, facilities and activities with sources of ionizing radiation developed by experts from the Regulatory Authorities of Argentina, Brazil, Chile, Cuba, Spain, Mexico, Peru and Uruguay, under the scientific coordination of the International Atomic Energy Agency (IAEA). Taking into account that Safety Culture problems have been widely recognised as one of the major contributors to many radiological events, several international and regional initiatives are being carried out to foster and develop a strong Safety Culture. One of these initiatives is the two-year project sponsored by the FORO with the purpose to prepare a document to allow its member states understanding, promoting and achieving a higher level of Safety Culture.

  4. Human factors in nuclear safety oversight

    International Nuclear Information System (INIS)

    Taylor, K.

    1989-01-01

    The mission of the nuclear safety oversight function at the Savannah River Plant is to enhance the process and nuclear safety of site facilities. One of the major goals surrounding this mission is the reduction of human error. It is for this reason that several human factors engineers are assigned to the Operations assessment Group of the Facility Safety Evaluation Section (FSES). The initial task of the human factors contingent was the design and implementation of a site wide root cause analysis program. The intent of this system is to determine the most prevalent sources of human error in facility operations and to assist in determining where the limited human factors resources should be focused. In this paper the strategy used to educate the organization about the field of human factors is described. Creating an awareness of the importance of human factors engineering in all facets of design, operation, and maintenance is considered to be an important step in reducing the rate of human error

  5. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  6. Safety Training: "Habilitation électrique - Non-Electrician - Initial" course in September

    CERN Multimedia

    Safety Training, HSE Unit

    2016-01-01

    The next "Habilitation électrique - Non-Electrician - Initial" course will be given, in French, on 12 September 2016.    This course is designed for anyone required to safely perform simple non-electrical operations. Grade of authorisation: B0-H0-H0V. There are places available. If you are interested in following this course, please fill in your EDH training request via our catalogue.

  7. Simulation study of coal mine safety investment based on system dynamics

    Institute of Scientific and Technical Information of China (English)

    Tong Lei; Dou Yuanyuan

    2014-01-01

    To generate dynamic planning for coal mine safety investment, this study applies system dynamics to decision-making, classifying safety investments by accident type. It validates the relationship between safety investments and accident cost, by structurally analyzing the causality between safety investments and their influence factors. Our simulation model, based on Vensim software, conducts simulation anal-ysis on a series of actual data from a coalmine in Shanxi Province. Our results indicate a lag phase in safety investments, and that increasing pre-phase safety investment reduces accident costs. We found that a 24%increase in initial safety investment could help reach the target accident costs level 14 months earlier. Our simulation test included nine kinds of variation trends of accident costs brought by different investment ratios on accident prevention. We found an optimized ratio of accident prevention invest-ments allowing a mine to reach accident cost goals 4 months earlier, without changing its total investment.

  8. Reactor safety: a discussion by officials of the Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Anders, W.A.; Rusche, B.C.; Stello, V. Jr.; Minogue, R.B.

    1976-01-01

    William A. Anders, Chairman of the Nuclear Regulatory Commission (NRC), and several senior officials spoke to the Joint Committee on Atomic Energy on the subject of nuclear safety, improvements in reactor plant safety, and quality assurance. The NRC, during its first year of organization, has developed new initiatives to improve safety and safeguards regulations. Anders stressed that NRC is not stifling internal discussion of opposing views, that it has been honest with the public, and that operating reactors are meeting rigorous safety standards. Other speakers discussed comparative safety of old and new reactors. Backfitting of older plants with new features is done when substantial safety protection can be added, but detuning an integrated system is not done indiscriminately. Officials of NRC do not agree with former General Electric employees, who testified that the regulatory procedure is inadequate. Safety improvements since August 28, 1962 and outlines of the review process are included in the Appendixes

  9. 78 FR 60877 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grants (T03), PAR-10-288, initial...

  10. 78 FR 60875 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grants (T03), PAR-10-288, initial...

  11. 77 FR 61756 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-10-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grant, PAR 10-288, initial review...

  12. Initial data on protective containment for safety analysis of NPP with WWER-1000 Preparation

    Directory of Open Access Journals (Sweden)

    Gubeladze Oleg

    2017-01-01

    Full Text Available In the presented article the nuclear safety issues with VVER-1000 reactor are considered. The study element is the protective containment (PC, the most important function of which is localization and retention of radioactive substances within the accident localization zone. The example of possible unregulated destructive forcing (UDF on the PC for the construction and installation work period is given.

  13. Focus on safety : a comparative analysis of pipeline safety performance 2000-2002

    International Nuclear Information System (INIS)

    2004-01-01

    Canada's National Energy Board (NEB) is responsible for the promotion of safety, environmental protection and economic efficiency in the Canadian public interest in regulating the design, construction, operation and abandonment of interprovincial and international pipelines within Canada. This second annual report provides a review of the safety performance of oil and gas pipeline companies that are regulated by the NEB. The data used to prepare this report originates from two sources: incident reports submitted under the Onshore Pipeline Regulations, 1999, and from information voluntarily provided by pipeline companies under the Safety Performance Indicators (SPI) initiative. Data comparisons with external reference organizations were included. Six key indicators have been identified to provide comprehensive measures of safety performance for pipeline companies: fatalities, ruptures, injury frequencies, liquid releases, gas releases, and unauthorized activities on the right of way. The safety performance of the federally regulated pipeline industry within Canada was satisfactory during this reporting period (2000-2002). The contractor injury frequency rates reported in 2002 were lower than those reported in 2001, and exhibited more consistency with the levels reported in 2000. The NEB is of the opinion that the elevated number of liquid hydrocarbon spills reported in 2000 were a result of elevated construction levels. No fatalities were reported. There was an increase to three from two in the number of ruptures, due in large part to metal loss (corrosion) and cracking, and external interference (third party damage). The number of spills increased to 76 in 2002 from 55 in 2001, which appears to be more in line with industry averages. The volume of hydrocarbon liquid released in 2002 represented one third the volume released in 2001. refs., 5 tabs., 14 figs

  14. The link between leadership and safety outcomes in hospitals.

    Science.gov (United States)

    Squires, Mae; Tourangeau, Ann; Spence Laschinger, Heather K; Doran, Diane

    2010-11-01

    To test and refine a model examining relationships among leadership, interactional justice, quality of the nursing work environment, safety climate and patient and nurse safety outcomes. The quality of nursing work environments may pose serious threats to patient and nurse safety. Justice is an important element in work environments that support safety initiatives yet little research has been done that looks at how leader interactional justice influences safety outcomes. A cross-sectional survey was conducted with 600 acute care registered nurses (RNs) to test and refine a model linking interactional justice, the quality of nurse leader-nurse relationships, work environment and safety climate with patient and nurse outcomes. In general the hypothesized model was supported. Resonant leadership and interactional justice influenced the quality of the leader-nurse relationship which in turn affected the quality of the work environment and safety climate. This ultimately was associated with decreased reported medication errors, intentions to leave and emotional exhaustion. Quality relationships based on fairness and empathy play a pivotal role in creating positive safety climates and work environments. To advocate for safe work environments, managers must strive to develop high-quality relationships through just leadership practices. © 2010 The Authors. Journal compilation © 2010 Blackwell Publishing Ltd.

  15. Reactor safety research in times of change

    International Nuclear Information System (INIS)

    Zipper, Reinhard

    2013-01-01

    Since the early 1970ies reactor safety research sponsored by the German Ministry of Economics an Technology and its predecessors and pursued independently from interests of industry or industrial associations as well as from current licensing issues significantly contributed to the extension of knowledge regarding risks and possible threats associated with the operation of nuclear power plants. The results of these research activities triggered several measures taken by industry and utilities to further enhance the internationally recognized high safety standards of nuclear power plants in Germany. Furthermore, by including especially universities in the distinguished research activities a large number of young scientists were given the opportunity to qualify in the field of nuclear reactor technology and safety thus contributing to the preservation of competence during the demographic change. The nuclear phase out in Germany affects also issues of reactor safety research in Germany. While Germany will progressively decrease and terminate the use of nuclear energy for public power supply other countries in Europe and in other parts of the world are continuing, expanding and even starting the use of nuclear power. As generally recognized, nuclear safety is an international issue and in the wake of the Fukushima disaster there are several initiatives to launch a system of internationally binding safety rules and guide lines. The German Competence Alliance therefore has elaborated a framework of areas were future reactor safety research will still be needed to support German efforts based on own and independent expertise to continuously develop and establish highest safety standards for the use of nuclear power supply domestic and abroad.

  16. Influencing Safety in Australian Agriculture and Fisheries.

    Science.gov (United States)

    McBain-Rigg, Kristin E; Franklin, Richard C; King, Jemma C; Lower, Tony

    2017-01-01

    Improving the health and safety of those working in Australian agriculture and fishery industries is a recognized priority area for preventative activities. With Australian agricultural industries being among the nation's most dangerous workplaces, there is a need for action. While there are currently known solutions, their implementation is limited. Influential agents, i.e., people who can influence others, are important for helping engender action to enact solutions into practice. This study examines agents that influence safety behavior either negatively (barriers) or positively (facilitators), in the Australian agriculture and fishery industries. Focus groups were conducted with producers and industry representatives. Thematic analysis identified barriers and facilitators to improve health and safety. These were assessed against the Socioecological Model, which considers the various, and often intersecting, human (intrapersonal, i.e. values and attitudes, peers, familial, and cultural) factors influencing safety behavior. Seven categories of human influences were identified: self, peers, family, intergenerational change, industry agents, government agents, and other. Peers (including direct managers) and family were seen to be direct influencers. Individuals signal to others that safety is valued and important. This is reinforced by experience, skill, attitudes, and behavior. Safety practice knowledge acquisition occurred via the family unit, specific training, industry, or knowledge transfer between industries. Government influence predominately focused on legislation and while the source of this influence is distant, it does influence behavior. There is a need to support comprehensive programs. These should include strengthening relationships via peer-to-peer networking, sharing information about safety initiatives, appropriate legislation, and enhancing leadership of all influencers with regard to safety.

  17. The development on the methodology of the initiating event frequencies for liquid metal reactor KALIMER

    International Nuclear Information System (INIS)

    Jeong, K. S.; Yang, Z. A.; Ah, Y. B.; Jang, W. P.; Jeong, H. Y.; Ha, K. S.; Han, D. H.

    2002-01-01

    In this paper, the PSA methodology of PRISM,Light Water Reactor, Pressurized Heavy Water Reactor are analyzed and the methodology of Initiating Events for KALIMER are suggested. Also,the reliability assessment of assumptions for Pipes Corrosion Frequency is set up. The reliability assessment of Passive Safety System, one of Main Safety System of KALIMER, are discussed and analyzed

  18. Overview of DOE/ONS criticality safety projects

    International Nuclear Information System (INIS)

    Barber, R.W.; Brown, B.P.; Hopper, C.M.

    1985-01-01

    The evolution of Federal involvement with nuclear criticality safety has traversed through the 1940's and early 1950's with the Manhattan Engineering District, the 1950's and 1960's with the Atomic Energy Commission, the early 1970's with the Energy Research and Development Administration, and the late 1970's to date with the US Department of Energy. The importance of nuclear criticality safety has been maintained throughout these periods; however, criticality safety has received shifting emphases in research/applications, promulgations of regulations/standards, origins of fiscal support and organization. In June 1981 the Office of Nuclear Safety was established in response to a Department of Energy study of the impact of the March 1979 Three Mile Island accident. The organizational structure of the ONS, its program for establishing and maintaining a progressive nuclear criticality safety program, and associated projects, and current history of ONS's fiscal support of program projects is presented. With the establishment of the ONS came concomitant missions to develop and maintain nuclear safety policy and requirements, to provide independent assurance that nuclear operations are performed safely, to provide resources and management for DOE responses to nuclear accidents, and to provide technical support. In the past four years, ONS has developed and initiated a continuing Department Nuclear Criticality Safety Program in such areas as communications and information, physics of criticality, knowledge of factors affecting criticality, and computational capability

  19. Occupational Safety and Health Management System (OSHMS)

    International Nuclear Information System (INIS)

    Shyen, A.K.S.; Mohd Khairul Hakimin; Manisah Saedon

    2011-01-01

    Safe work environment has always been one of the major concerns at workplace. For this, Occupational Safety and Health Act 1994 has been promulgated for all workplaces to ensure the Safety, Health and Welfare of its employees and any person at workplaces. Malaysian Nuclear Agency therefore has started the initiative to review and improve the current Occupational Safety and Health Management System (OSHMS) by going for OHSAS 18001:2007 and MS 1722 standards certification. This would also help in our preparation to bid as the TSO (Technical Support Organization) for the NPP (Nuclear Power Plant) when it is established. With a developed and well maintained OSHMS, it helps to create a safe working condition and thus enhancing the productivity, quality and good morale. Ultimately, this will lead to a greater organization profit. However, successful OSHMS requires full commitment and support from all level of the organization to work hand in hand in implementing the safety and health policy. Therefore it is essential for all to acknowledge the progress of the implementation and be part of it. (author)

  20. Patient Safety Movement: History and Future Directions.

    Science.gov (United States)

    Lark, Meghan E; Kirkpatrick, Kay; Chung, Kevin C

    2018-02-01

    Despite progress within the past 15 years, improving patient safety in health care remains an important public health issue. The history of safety policies, research, and development has revealed that this issue is more complex than initially perceived and is pertinent to all health care settings. Solutions, therefore, must be approached at the systems level and supplemented with a change in safety culture, especially in higher risk fields such as surgery. To do so, health care agents at all levels have started to prioritize the improvement of nontechnical skills such as teamwork, communication, and accountability, as reflected by the development of various checklists and safety campaigns. This progress may be sustained by adopting teamwork training programs that have proven successful in other high-risk industries, such as crew resource management in aviation. These techniques can be readily implemented among surgical teams; however, successful application depends heavily on the strong leadership and vigilance of individual surgeons. Copyright © 2018 American Society for Surgery of the Hand. Published by Elsevier Inc. All rights reserved.